ML19312D896

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Forwards Response to NRC Requesting Info Re Containment Environ Conditions & Sys Required for Accident Mitigation
ML19312D896
Person / Time
Site: Haddam Neck, Millstone  File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 05/01/1980
From: Counsil W
CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO.
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
TASK-03-12, TASK-3-12, TASK-RR NUDOCS 8005050331
Download: ML19312D896 (10)


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,""CCl May 1, 1980 Docket Nos. 50-213 50-245 Director of Nuclear Reactor Regulation Attn:

Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 U. S. Nuclear Regulatory Commission Washington, D. C.

20555

References:

(1)

D. L. Ziemann letter to W. G. Counsil dated March 28, 1980.

(2)

W. G. Counsil letter to D. L. Ziemann dated April 29, 1980.

(3)

W. G. Counsil letter to D. L. Ziemann dated January 30, 1980.

Gentlemen:

Haddam Neck Plant Millstone Nuclear Power Station, Unit No.1 Environmental Qualification of Electrical Equipment In Reference (1), the Staff clarified its informational needs and submittal dates with respect to containment environmental conditions and systems required for accident mitigation. The latter request was fulfilled for both operating units by Reference (2). Regarding containment environmental conditions, the following information is hereby provided, pursuant to the Staff's 10CFR50.54 (f) request.

Regarding Millstone Unit No.1, Reference (1) requires no formal documenta-tion at this time.

However, as discussed between members of our respective S,taffs in recent telephone discussions, it is Northeast Nuclear Energy Company's (NNECO) intention to justify the use of a less severe environmental profile than that specified in the NRC guidelines for Boiling Water Reactors.

l NNECO will continue to keep the Staff appraised regarding the specific l

analysis and schedules for formalizing this justification.

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Regarding the Haddam Neck Plant, a formal response to Reference (1) was l

requested and is provided in Attachment 1.

As previously verbally communicated I

to the Staff, it is our current intention to follow the guidance identified in Item 6.B of Enclosure 1 to Reference (1). Specifically, utilization of the steam line break analysis results submitted previously to the Staff in Reference (3) is intended to justify the use of the most current approved LOCA analysis for the limiting environmental profile. Accordingly, the l

attached information references the most current LOCA analysis on the docket in defining the service conditions to be used in equipment qualification.

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_2-It is currently envisioned that additional extrapolations and supporting calculations will justify adoption of the above approach.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTilEAST NUCLEAR ENERGY COMPAh7 l-W. G. Counsil Vice President At tacluaent l

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STATE OF CONNECTICUT )

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jfpg COUNTY OF HARTFORD

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j Then personally appeared before me W. G. Counsil, who being duly sworn, did state that he is Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.

) S. h Notary Public

% Commission Exp;ns March.1,1;31 l

DOCKET No. 50-213 ATTACHMENT 1 HADDAM NECK PLANT RESPONSE TO ENCLOSURE 2 l

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MAY, 1980

4 ATTACHMENT 1 HADDAM NECK PLANT RESPONSE TO ENCLOSURE 2 1.

The results of the most current LOCA analysis for the Haddam Neck Plant can be found docketed in Section 3 of the Connecticut Yankee FDSA.

Since the actual calculations which lead to the docketed results are not available and the information contained in Section 3 does not detail all the information requested, the FDSA information has been l

supplemented by information generated internally by CYAPCO.

A.

The Connecticut Yankee Containment Net Free Volume is 2,232,000 cubic feet.

B.(1, 2) A listing of major passive heat sinks within the containment has been generated by CYAPCO and follows for your information:

1) Containment Cylinder + 3/8" carbon steel plate liner (painted) -- 6 mil finish paint and 3 mil. primer (assumed),

4'6" thick concrete, outside surface to atmosphere, lower 17 feet insulated --

therefore, no heat transfer assumed for this area. Total active heat transfer area (oce side) is 43,472 square feet.

2) Containment Dome + 1/2" carbon steel plate liner (painted) -- 6 mil. finish paint and 3 mil. primer (assumed), 2'6" thick concrete, outside surf ace exposed to atmosphere, 28,627 square feet surface area (one side).
3) Refueling Water Cavity Walls + 3/8" carbon steel plate liner on one side (painted),10 mil. finish paint and 3 mil. primer (assumed), 4'0" thick concrete wall - unlined surface painted, 6 mil.

finish paint (assumed) 6,916 square feet surface area (two sides).

4) Fuel Transfer Canal + 3/8" carbon steel plate liner on one side (painted),10 mil. finish paint and 3 mil. primer (assumed), 5'9" thick concrete wall - unlined surface painted, 6 mil. finish paint (assumed) 7,420 square feet surface area (two sides).

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5) Vertical Concrete Wall near Charging Station +

3'6" thick concrete, 6 mil. finish paint (assumed),

1800 square feet surface area (two sides).

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6) Crane Wall + 3.0' thick concrete, 6 mil. finish paint (assumed),15,651 square feet surface area l

(two sides).

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7) Vertical Concrete Walls Separating Loops 1-2 and 3-4 + 1'6" thick concrete, 6 mil. finish paint (assumed), 4,320 square feet surface area (two sides).

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8) Outer Annulus Walkways + 1'0" thick concrete, 6 mil. finish paint (assumed), 23,898 square feet surface area (two sides).
9) Primary Shield Wall + 4'6" thick concrete, 6 mil.

finish paint (assumed), 1,700 square feet surface l

area (one side).

10)

Steam Generator Skirts + l-1/2" thick carbon steel plate (painted), 6 mil. finish paint and 3 mil.

primer (assumed), 14,426 square feet surface area (two sides).

11) Neutron Shield Tank + 1" Average thickness carbon steel plate tank, 6 mil. finish paint and 3 mil. primer (assumed), 2,158 square feet exposed surface area (one side).
12) Steel Grating - Galvanized + 3/16" average thickness, 0.0034 inch zine plating (assumed), 7,119 square feet exposed surface area (both sides).
13) Steel Beams, Outer Annulus, (.18" < t <

4") +

Average Thickness = 0.312", 6 mil. finish paint and 3 mil. primer (assumed), 6,785 square feet exposed surface area (both sides).

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Steel Beams, Outer Annulus, (.4" < t < 1.0") +

l Average Thickness = 0.501", 6 mil. finish paint, and 3 mil, primer (assumed),10,647 square feet exposed surface area (both sides).

B.(3)

Thermo-physical properties +

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1) Carbon Steel:

29.6 Btu /hr-ft-F, 53.6 Btu /ft _op 3

2) Concrete: 1.04 Btu /hr-f t *F, 35.86 Btu /f t _op l

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3) Zinc: 62.2 Btu /hr-ft-F, 42.0 Btu /ft _op i

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4) Finish Paint:

0.5 Btu /hr-ft-F, 31.2 Btu /ft - F i

5) Primer: 1.24 Btu /hr-ft-F, 27.3 Btu /ft - F i

C)

Initial Containment Conditions i

1) Temperature = 90* - 130 F (Normal Operating Range) 3
2) Pressure

= 1.5 - 2.0 psig (Normal Operating Range)

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3) Humidity

= 40 - 70% R.H. (Normal Operating Range)

D)

Containment Spray System 1

The containment spray system requires manual initiation and, therefore, is not taken credit for in the accident situation. The request for information is, therefore, i

not applicable.

E)

Fan Cooler System

1) Maximum delay time before the fan cooler becomes effective for heat removal, assuming a loss of offsite power is 60 seconds.

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2) Heat removal capability per cooler follows:

Temperature Heat Removal Rate 183 F 20 x 106 Btu /hr i

220 F 30 x 106 Btu /hr 243 F 40 x 106 Btu /hr 261 F 45 x 106 Btu /hr F)

Not Applicable.

G)

The docketed FDSA containment pressure analysis description does not address single failures as would be required in present-day analyses, due to changes in criteria since the analyses were performed. Results are shown in i

I Figure 3.2-1 of the Connecticut Yankee FDSA for various combinations of operable and inoperable emergency safe-guards features.

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Efforts are currently underway to obtain mass and energy release data for the docketed analysis. We will keep you advised of our progress in this regard, and anticipate that a response can be provided on or before the date of the site audit.

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