ML17037B962

Letter Advising That the Unit 2 Containment Will Be Evaluated Based on the Mark II Containment Dynamic Forcing Function Report (Dffr) and the Attached Table 5.2-1 and the Results Will Be Submitted in June, 1976

ML17037B962
Person / Time
Site:	Nine Mile Point
Issue date:	12/30/1975
From:	Schneider R Niagara Mohawk Power Corp
To:	Stolz J Office of Nuclear Reactor Regulation
References
NEDE-21061P, NEDO-21061
Download: ML17037B962 (8)

Text

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NRC 'TRIBUTION FOR PART EO DOCI<QMATERIAL (TEMPORARY FORM)

CONTROL NO:

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Syracuse, NY der 12-30-75 1-5-76 DATE OF DOC DATE REC'D LTR TWX BPT OTHER TO:

CLASS Mr Stolz UNCLASS XXKGKXX PROP INFO ORIG

.one signed INPUT CC OTHER NO CYS REC'D

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50-410 DESC R IPTION:

. Ltr re their 10 3-75 ltr.."...furnishing info con mark II containment 4ynamic forcing. functional report,.

which was forwarded -to us by, CE in late'.

October of 1975..;..w/pttchment's.....;....

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NIAGARA MOHAWK POWER CORPORATION NIAGARA~

MOHAWK 300 ERIK 80UI.KVARO WEST SYRACUSE, N.Y. IS202 PEICYPEQ VSIIRC JAN 5 1976~

Mall Seel December 30, 1975 Director of Nuclear Reactor Regulation Attention: Mr. J.. F. Stolz, Chief Branch 2-1 U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Be:

Nine Mile Point - Unit 2 Docket No. 50-410

Dear Mr. Stolz:

Our October 3, 1975, letter indicated that a report entitled "Mark II Containment Dynamic Forcing Functions Report" (DFFR) would be for-warded to you by the General Electric Company by late October, 1975.

That report, consisting of NEDO-21061 and NEDE-21061P, was forwarded via an October 24, 1975 letter from Mr. I. F. Stuart, (General Electric),

to Mr. R. S. Boyd, (Commission).

The report contains descriptions of phenomena to be used as a design basis for the Nine Mile Point Unit 2 containment.

Specific load combinations for the Unit 2 containment are attached.

This data sup-plements Table 5. 2-1 of the DFFR.

This completes the requirements for Part 1 of the Program and Schedule, enclosed with our June 20, 1975 letter.

The Nine Mile Point Unit 2 containment will be evaluated based on the DFFR and the attached table.. The results of this evaluation will be submitted in June, 1976, in accordance with Part 3 of our Program and Schedule.

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Mr. J. F. Stolz 0 ember 30, 1975 In addition, Part 2 of our Program and Schedule indicated that information pertaining to pool temperature considerations would be provided by December, 1975.

Due to additional supporting work re-quired, however, we-will be unable to meet that date.

Portions of this information willbe provided in June, 1976, with the balance included in the Final Safety Analysis Report.

Very truly yours, NIAGARA.MOHAWKPOWER CORPORATION

. R. Schneider Vice President - Electric Operations plb Attachment

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NI E MILEPOINT UNIT 2 TAB~5. 2-1 I

Load Combination for the Nine Mile Point 2 Containment Considerin H drodynamic Loads LOAD.

EQN.

COND.

D 1

Normal 1.4 w/o Temp.

L F

Po To 1.7 1.0 1.0 Ro Eo Ess PB PA TA. RA Rr SRV 1.5 2

Normal

1. 0 w/ Temp.

1.3 '.0 1.0 1.0 1.0 103 3

Normal

1. 0 Sev. Env.

1.0 1.0 1.0 1.0 1.0 1.25

1. 25 4

Abnormal l. 0

1. 0

1. 0 1.25 -

1.0 1.0 1.25 4a Abnormal 1. 0

1. 0

1. 0 1

25 1

0 1

0 1

Ov 5

Abnormal1.0 1.0 1.0

1.1 1.1 1.0 1.0 1.1 Sev. Env.

II 5a Abnormal10 10 10 11 11 11 11 10<

Sev. Env.

6 Normal 10 10 10 10 10 10 10 Ext. Env.

1.0 7

Abnormal1.0 1.0 1.0 Ext. Env.

1.0 1.0 1.0 1.0 1.0 1.0 7a Abnormal 1. 0

1. 0

1. 0 Ext. Env.

1 ~ 0 1 ~ 0 1 ~ 0 1 ~ 0 1 ~ 0 1 ~ 0"'c Load Descri tion Sev. Env.

Ext. Env.

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p PQ TQ RQ Severe Environment E

Extreme Environment Ess Dead Loads PB Live Loads Prestressing Loads TA Operating Pressure Loads RA Operating Temperature Loads Operating Pipe Reactions Rr SRV Operating-Basis Earthquake Safe Shutdown Earthquake SBA. or IBA. Pressure Load DBA. (LOCA) Pressure Load Pipe Break Temperature Load Pipe Break Temperature Reaction Loads Reaction and jet forces associated with the pipe break Safety/Relief Valve Loads

." In these combinations the SRV load is that associated with the discharge of one valve simultaneously with the LOCA. to satisfy the single failure criterion.

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