ML19323A444

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Forwards Info Per NRC 800214 Request,Supporting Confirmatory Piping Analysis of Safety Relief Valve 16,discharge Line. Revision 6 to Piping Design Spec 9645-M-220.0,other Supporting Info & Drawings Available in Central Files Only
ML19323A444
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 04/09/1980
From: Dale L
MISSISSIPPI POWER & LIGHT CO.
To: Houghton T
Office of Nuclear Reactor Regulation
Shared Package
ML19323A445 List:
References
NUDOCS 8004210228
Download: ML19323A444 (4)


Text

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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi Edhhihldidd5 P. O. B O X 16 4 0, J AC K S O N. MIS SIS SI P PI 3 9 2 0 5 P 8t O D U C T I O N DEPARTMENT April 9, 1980 U. S. Nuclear Regulatory Commission Light Water Reactors Branch No. 2 Division of Project Management W shington, D. C.

20555 ATTENTION:

Mr. Thomas C. Houghton

Dear Mr. Houghton:

SUBJECT:

Grand Gulf Nuclear Station Dockets 50-416 and 50-417 Units 1 and 2 File 0272/0277/L-334.C Confirmatory Piping Analysis by NRC Consultant - Request for Information AECM-80/61 The letter from Mr. Robert L. Baer of February 14, 1980, requested information to support the confirmatory piping analysis of the #16 SRV discharge line being performed by Pacific Northwest Laboratory as part of the Grand Gulf operating license review.

Below are listed the specific requests frca Mr. Baer's letter with a description of those items attached in response.

Note that some items will be provided by separate letter.

1.

Piping layout and isometric drawings sufficient to model the system--

a.

Drawing 9645-SK-M-4004, Revision A, System Piping i

Isometric, Main Stream "C" SRV to Suppression Pool--

Containment, Unit 1 (Attachment 1).

b.

Specification 9645-MS-01, Revision 9, Grand Gulf Nuclear Station, Units 1 and 2, Valve Identifica-tion (Attachment 2).

\\

2.

Support drawings with support and hanger spring rates--

a.

Support drawings will be provided by separate 4\\ [*'

dy [.

\\

letter.

b.

Spring rates are stated on drawing 9645-SK-M-4004, O

0 9

Revision A (l.a above).

p

[

8004210 g

Member Middle South Utilities System

Mississippi POWER O LIGHT COMPANY Mr. Tom Houghton AECM-80/61 U. S. Nuclear Regulatory Commission Page two 3.

Piping design specification--

a.

Applicable portions of piping design specification 9645-M-220.0, Revision 6, Design Specification for Nuclear Piping Systems for Mississippi Power and l

Light Company, Grand Gulf Nuclear Station, Units 1 and 2, Grand Gulf, Mississippi (Attachment 3).

b.

Piping data is listed on drawing 9645-SK-M-4004, Revision A (1.a above).

4.

Valve weights and CG's--

l Drawing 9645-M-157.1-14006-01-H, Revision 5, 10 In. 300#

W. E. Vacuum Breaker Valve (Attachment 4).

i 5.

Appropriate response spectra--

Five dynamic load cases are provided (Attachment 5).

a.

b.

For each load case, information is provided at three or four el.?vations, as appropriate.

c.

For each load case, an envelope of spectra at all ap-1 propriate elevations is also provided (Attachment 6).

6.

Appropriate anchor point movements-Information is provided on drawing 9645-SK-M-4004, Re-vision A, Assumption 1 (1.a above).

7.

Any design change notices not yet incorporated into the piping or support drawings--

a.

There are no outstanding design change notices, as i

of this date.

b.

All subsequent design change notices applicable will be forwarded for your information.

8.

Suppression pool drag loads necessary to analyze the submerged portions of the line--

i a.

Calculation 9645-8.8.16-Q, Revision A, Loads on

{

Quencher Resulting from Air Clearing, Sheets 14 through 16 (Attachment 7).

l b.

This calculation gives the loads for a quencher that i

are imposed by the air clearing of an adjacent quencher. The air clearing of an adjacent quencher is the limiting load for the quencher when consi-dered as a submerged structure. The case shown in

[

i

.the attached load sheets (8.a above) is for a situation where the quenchers are located 16 degrees apart around the drywell circumference.

There are l

r l

~

^

~ MISSISSIPPI POWER Q LI"2HT COMPANY Mr. Tom Houghton AECM-80/61 U. S. Nuclear Regulatory Commission Page three f

other situations where the distance between quenchers is greater. These situations do not need to be ad-dressed since the load on the adjacent quencher de-creases with distance by the following relationship:

P Br distance between P=

where r

=

quenchers 4.87 feet r

=

c attenuated bubble

?

=

pressure from one SRV at distance r PB quencher bubble

=

pressure i

The loads identified do not contain any dynamic load factors. A factor, as noted below (9), will be used for the piping analysis.

9.

Dynamic load factors necessary to analyze the submerged por-tions of the line--

The dynamic load factor that was used is provided on drawing 9645-SK-M-4004, Revision A, Assumption 2 (1.a above) 10.

The relief valve time history has also been provided for your use (Attachment 8).

11.

Drawings 9645-M-101.1-D-76-717, Revision 11, Main Steam Safety / Relief Valve Discharge Line Quencher and 9645-M-101.1-D-76-718, Revision 5, Miscellaneous Details have also been provided for your use (Attachments 9 and 10).

If you have any questions concerning the attached information or need further information, please advise. The points of contact within our supporting architect engineering organization, Bechtel Power Cor-poration, are Mr. M. J. David, Licensing, and Mr. H. M. Brooks, Licensing.

Yours truly,

/

L

,l g /' L. F. Dale j

Nuclear Project Manager JGC/HMB:ts e

Attachments:

1.

Drawing 9645-SK-M-4004, Revision A 2.

Specification 9645-MS-01, Revision 9 (Attachments continued on next page)

MISSISSIPPI POWER Q LI2HT COMPANY Mr. Tom Houghton AECM-80/61 U. S. Nuclear Regulatory Commission Page four Attachments Cont'd:

3.

Applicable portions of specification 9645-M-220.0, Revision 6 4.

Drawing 9645-M-157.1-14066-01-H, Revision 5 5.

Response spectra 6.

Envelope of response spectra 7.

Calculation 9645-8*.8.16-Q, Revision A, Sheets 14 through 16 8.

Relief valve time history 9.

Drawing 9645-M-101.1-A-76-717, Revision 11 10.

Drawing 9645-M-101.1-A-76-718, Revision 5 cc:

Mr. N. L. Stampley Mr. R. B. McGehee Mr. T. B. Conner Mr. Victor Stello, Jr., Director Division of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Mr. Merv Bampton Pacific Northwest Laboratory Richland Boulevard Richland, Washington 99351 t

l

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