ML17037B583

Letter and Attachment Containing Information Concerning Relief Valve Actuations Following a Postulated Isolation Event

ML17037B583
Person / Time
Site:	Nine Mile Point
Issue date:	07/26/1978
From:	Dise D Niagara Mohawk Power Corp
To:	Stello V Office of Nuclear Reactor Regulation
References
Download: ML17037B583 (14)

Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM <RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-220

~REC:

STELLO V

ORG:

DISE D P DOCDATE: 07/26/78 NRC NIAGARA MOHAWK PWR DATE RCVD 07/31/78 DOCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1

ENCL 1

RESPONSE

TO NRC LTR DTTD 03/20/78...

FORWARDING INFO CONCERNING RELIEF VALVE ACTUATIONS FOLLOWING A POSTULATED ISOLATION EVENT FOR SUBJECT FACILITY.

PLANT NAME: NINE MILE PT " UNIT 1

REVIEWER INITIAL:

XJM DISTRIBUTOR INITIAL:

~>+~>>++<<H>+~HHH>++~> DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRIBUTION CODE A001)

FOR ACTION:

INTERNAL:

EXTERNAL:

BR CHIEF=ORBN3 BC+4W/7 ENCL EG FgL 4~W/ENCL I~E++W/2 ENCL ISANAUER~~W/ENCL AD FOR SYS 0 PROJ+~W/ENCL REACTOR SAFETY BR++W/ENCL EEB~+W/ENCL J.

MCGOUGM++W/ENCL LPDR'S OSWEGO<

NY+>W/ENCL TERA+4W/ENCL NS IC++W/ENCL ACRS CAT B~~W/16 ENCL NRC PDR++W/ENCL GELD>+LTR ONLY CORE PERFORMANCE BR+~W/ENCL ENGINEERING BR+>W/ENCL PLANT SYSTEMS BR+<A/ENCL EFFLUENT TREAT SYS>>W/ENCL DISTRIBUTION:

LTR 40 ENCL 39 SIZE:

1P+SP THE END CONTROL NBR'82120040

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NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE. N.Y. 13202/TELEPHONE (315) 474-1511 July 26, 1978 Director of Nuclear Reactor Regulation Attn:

Mr. Vic'tor Stello, Jr., Director Division of Operating Reactors U.

S. Nuclear Regulatory Commission Washington, D.

C.

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Gentlemen:

Re:

Nine Mile Point Unit 1 Docket No. 50-220 DPR-63 Pursuant to your letter of March 20,

1978, the attachment to this letter contains the information concerning relief valve actuations following a postulated isolation event for Nine Mile Point Unit 1.

The analyses show that stresses for the torus shell and support columns are within ASME code 'allowables, even if all six relief valves experience.,subsequent actuation.

General Electric, in a letter. dated July 21, 1978 from L. J.

Sobon (General Electric) *to Mr. Victor Stello, Jr.

(Nuclear Regulatory Commission),

submitted information con-cerning the generic approach for c'alculating the above plant-unique column and'shell loads.

Very truly yours, NIAGARA MOHAWK POWER CORPORATION Donald P. Disc Vice President-Engineering MGM/szd Attachment

',782120040

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NINE NILE POINT UNIT 1 MJLTIPLE CONSECUTIVE S/RV ACTUATION EVALUATION

A TELEDYNE ENGliNEERlNG SERVICES Nine Nile Point Nuclear Power Station Multi le Consecutive S/RV Actuation Evaluation

~

6 SRV lines assume multiple consecutive actuation of all valves

~ determination of the maximum shell stress and support column load for the torus segment containing relief line l-ll 1-070 1-09

-.0 270'-08Q 1-100'0

.0 1-12 0

1-11

'I

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~

Location A

~,

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P< T 'YNE E

}NEER)NGSERV!CES Shell St'ress Determination Factor for Multiple Actuation:

Multiplier for Multiplier for Multiplier for Multiplier'for Multiplier for Multiplier for.

Rel ief Line Relief Line Relief Line Relief Line 1-11

= 1.0 1-12

=

.19'-08

=.11 1-07

=

.11 Relief Line 1-09

=

.11 Relief Line 1-"10 =.11 Hei: Hultip'lier =(1.2)(SRSS)=

1.2497 Hot Pop Multiplier = 2.37 Plant Unique Shell Stress Multiplier =.28

.From Monticello S/RV Test - Single Cold Actuation of Valve D:

Extreme Fiber Shell Stress at Midbay, 45'p from bottom toward inside columns

= 3400 psi Factor relating stress at bottom midbay to stress 45'p from bottom midbay = 1.49 Nine Mile Point Torus Radius

= 162 in.

Monticello Torus Radius

= 166 in.

Nine Mile Point Torus Thickness

=.460 in.

Monticello Torus Thickness

=.584 in.

'Resultant SRV Shell Stress (PL + P>)

=

) '( 4

) 1'9 '60 166 5205 psi

~

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a A TELEDYNE EMGINEERINQSERVICES Factor from extreme fiber to membrane stress

=.86 Resultant SRY Shell Stress (PM)

= (.86)(5205)

= 4476 psi Hydrostatic Pressure Stress at O'owncomer Submergence

= 1771 psi (including Seismic)

Total Shell Stress:

Membrane, PH

= 4476 + 1771

= 6247 psi Hembrane

+ Bending, PL +

P

= 5205

+ 1771

= 6976 psi B

Shell Material:

A-201B FBX ASHE Code Allowable Stress:

P S

= 16,500 psi M

mc PL + PB

< 1.5 S

= 24,750 psi mc Fraction of Code Allowables:

PM

+38 PL +

PB.28 Su ort Column Load Determination Factor for Multiple Actuation:

Location

'A

0

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A TDYNE ENGINEERING SERVICES Multiplier for Relief Line 1-09

=

Multiplier for Relief Line 1-10

=

Multiplier for Relief Line l-ll =

Multiplier for Relief Line 1-12

=

Multiplier for Relief Line 1-08

=

Multiplier for Relief Line 1-07

=

.12 1.0

.7

.09 2.12 Consecutive Actuation Factor

= 1.96,.

Plant Unique Column Load Multiplier =.30

'I From Monticello Rams Head SRY Test, Single Cold Actuation:

Outs i de Column Compress i ve Load = 196. 7 kips Resultant SRY Column Load

= (.30)(196.7)(2,12)(1.96)

= 245 kips 1

- Outside Column Deadweight

+ Seismic

= 200 kips Total Outside Column Compressive Load

= 245 + 200

445 kips Outside Column'.ASME Code A11owable.

579 kips Outside Column Fraction of Code Allowable =.77

'Column Held Joint ASME Code Allowable = 678 kips Column Held Joint Fraction of Code Allowable =.66

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