ML17244A818

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Provides Submittal Schedule for SEP Mechanical Sys Equipment Items Still Outstanding Re Seismic Review.Submits Info Requested Re Equipment in Intermediate Bldg.Three Oversize Drawings Available in Central Files
ML17244A818
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/12/1979
From: White L
ROCHESTER GAS & ELECTRIC CORP.
To: Ziemann D
Office of Nuclear Reactor Regulation
References
TASK-03-01, TASK-RR NUDOCS 7909190365
Download: ML17244A818 (12)


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EXTERNAL: 03 LPDR 20'CRS 1

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I REGULATO Y IN MATION DISTRIBUTION SYtSq'l

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ACCESSION

.NBR /909190305, DOC.DATE: 79/09/12 NOTARIZED:

NO DOCKETS FACIL;50 244 Robert Emmet Ginna Nuclear Pl anti Unit 1'r Rochester G

05Wb244 AUTH,gAME AUTHOR AF F ILIATI ON l'

~WHITE e L ~ DB Roch'ester Gas,8 Elbctric Cor'p

'RECIP ~ NAME RECIPIENT AFFILIATION J

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Operating Reactors Branch 2

SUBJECT; Provides submittal schedule forfsystematic evaluation I

pr"ogr'am mechanical sys equipmen't items still outstanding re seismic reviewBSubmjts info requested re equipment in intermediate bldgBH/three oversize drawings.

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TITLE: Seismic Review for SEP Plants Ig NDTEB: r,Q:. W 444g4;<C, 4 Ad&mgy~~;

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UNITEDSTATES i UCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 MEDORAÃ)UM FOR:

TERA Corp.

US NRC/TEDC/Distribution Services Branch

SUBJECT:

Special Document Handling Requirements a

1 Please use the following special distribution list for the attached.

document.

The attached document requires the following. special considerations:

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ly&oversize enclosure was received - please return for Regulatory File storage.cft Ih[ C Q Pzoprietary infozuation send arfidavit only to the ttRC PDR Q Other: (specify) cc:

DSB Files TI33C/DSB Authorized Signature

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zznm ROCHESTER GAS AND ELECTRIC CORPORATION

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89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHlTE. JR.

VICE PRESIDENT TELEPHONE ARE* cooK 7le 546.2700 September 12, 1979 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis L. Ziemann, Chief Operating Reactors Branch No.

2 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Systematic Evaluation Program - Seismic Review R.

E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Ziemann:

Enclosure I of my letter of July 3, 1979 indicated submittal dates for information relating to the mechanical systems and equipment requested by the NRC for the Systematic Evaluation Program -Seismic Review for Ginna Station.

My correspondence of July 16, 1979 indicated that because of outstanding IE Bulletin responses, it was necessary to review our current. engineering manpower commitments including SEP seismic review input.

Accordingly, enclosure I provides a new submittal schedule for the SEP mechanical systems and equipment items still outstanding.

Also, a meeting on the SEP-seismic structural model was held at Reading, Pennsylvania on August 30, 1979 involving RG&E, Gilbert Associates, Lawrence Livermore Labs and the NRC (Mr. Tom Cheng).

As requested at that. meeting, RG6E gave Mr. Cheng a set of drawings of Ginna Station indicating the location and weight of major equipment loads.

Information was also requested relating to Cat. I equipment in the intermediate building and the structural framing on the east wall of the facade.

Enclosure II provides the requested information on the intermediate building.

A field inspection of the facade steel shows that drawing No. D-521-071 is correct as is.

To the best of our knowledge, this completes all currently outstanding structural seismic items.

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D. White, Jr.

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>909L90gg~ 0 Enclosure If there are any questions regarding this information, please contact us.

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ENCLOSURE I S stematic Evaluation Pro ram Seismic Review Submittal Schedule for Mechanical S stems and E ui ment I

1.

Essential Service Water Pumps:

Verification of the installation and seismic integrity will be submitted about October 1.

2.

Component Cooling Water Surge Tank:

Installation has been verified as per GAI Dwg. 5D-522-031 and Westinghouse Dwg. 5684-J-700 (submitted to NRC via 7-3-79 correspondence).

The seismic design summary of the equipment supports will be submitted about October 1.

3.

Component Cooling Water Heat Exchanger:

Installation has been verified as per GAI Dwg. 5D-522-031 and Atlas Manufacturing Co.

Dwg. SD-1260-7 (Enclosed).

The seismic design summary of the equipment supports will be submitted about October 1.

4.

Diesel Generator Air Tanks:

Installation verification and seismic design summary will be submitted about October 1.

5.

Boric Acid Storage Tank:

Installation has been verified as per GAI Dwg. 5D-422-304 and Westinghouse Dwg. 5684J809 (submitted to NRC via, 7-16-79 correspondence).

The seismic design summary will be submitted about October 1.

6.

Refueling Water Storage Tank:

Installation verification and seismic design summary will be submitted about October 1.

7.

Motor Operator Valves (electric/air) on lines 4" diameter and under.Details of typical installation and verification of seismic integrity will be submitted about October 1.

8.

Primary Equipment Inside Containment:

The equipment. seismic design summaries were submitted via the 7-16-79 correspondence.

The seismic design summaries for the equipment supports and the support drawings will be submitted about October 1.

Installation verification will be done during the next plant outage.

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Interaction of Seismic and Non-Seismic Equipment:

a.

HVAC in diesel generator room:

Installation verification and design summary will be submitted about October 1.

b.

Steel platform over oil feed line in diesel generator room:

Installation has been verified per GAI Dwg. 5D-502-075 (enclosed).

The design summary will be submitted October l.

10.

RHR System Dynamic Analysis (inside containment):

A summary of the RHR dynamic analysis was submitted to the NRC in response to IE Bulletin 79-07 (see cor-respondence L. D. White to D. L. Ziemann, dated 7/26/79).

The as-built piping isometric and support drawings are being completed in response to IE Bulletin 79-14.

These drawings and the piping system design date necessary for NRC analysis of the as-built condition.will be submitted about. October 15.

Main Steam System Dynamic Analysis (inside containment):

A summary of the main steam dynamic analysis was submitted to the NRC in response to IE Bulletin 79-07 (see cor-respondence dated 7/26/79).

The as-built piping isometric and support data are being completed in response to IE Bulletin 79-14.

These drawings and the piping system design data necessary for NRC analysis will be submitted about October 15.

12.

Chemical and Volume Control System (outside containment):

As-built piping isometrics and support drawings are currently being prepared in response to IE Bulletin 79-14.

These drawings and design data necessary for analysis will be submitted about November 15.

13.

Sample Cat. I 2" Diameter Field Run Piping:

As-built piping isometrics and support drawings are cur-rently being prepared in response to IE Bulletin 79-14.

These drawings and design data necessary for analysis will be submitted about November 15.

ENCLOSURE II The intermediate building and the control building have vital Category I equipment located on steel frame supported floors.

This equipment is:

Intermediate Buildin El 278'4" Steam Lines (including NSIV's, Safeties, Atmospheric

Reliefs,

+ TD AFN Steam Admission Valves)

El 298'4" Containment Purge System up to Containment Isolation Valves.

Control Buildin El 271'4" Relay Room El 298'4" Control Room

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