ML19309G689

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Forwards Data Requested for Calculation of Containment Pressure & Temp Decay.Info Represents Most Current LOCA Analysis
ML19309G689
Person / Time
Site: Yankee Rowe
Issue date: 05/01/1980
From: Vandenburgh D
YANKEE ATOMIC ELECTRIC CO.
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
WYR-80-48, NUDOCS 8005070368
Download: ML19309G689 (13)
v • d • e


Text

8005070 3 67 O

Telephone e17 366-90ll TwX 710 390-0739 YANKEE ATOMIC ELECTRIC COMPANY n.3.2.1 WYR 80-48

]

20 Turnpike Road Westborough, Massachusetts 01581

.Yauxse May 1, 1980 United States Nuclear Regulatory Commission Washington, D. C.

20555 Attention:

Division of Licensing Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5

Reference:

(a) License No. DPR-3 (Docket No. 50-79).

(b) UStGC T.etter to YAEC, dated March 28, 1980.

(c) YAEC Letter to USAEC, dated August 6, 1971, PC-96.

Subject:

Data for Calculation of Containment Pressure and Temperature Decay

Dear Sir:

The information requested in Enclosure 2 of Reference (b) is provided in Attachment A to this letter. Environmental conditions currently used for electrical equipment qualification at Yankee Rowe are defined by the containment pressure and temperature analysis submitted to the staff in Reference (c), which represents the most current LOCA analysis on the docket for the purpose described above. The data, tabulated and described in the attachment, has been extracted from that submittal.

We trust you will find this information satisfactory. However, if you 0409008 l

Unitsd Sectso Nuciscr R2gulctory Commicsien Mr. Dennio M. Crutchfisid, Chief May 1, 1980 Page 2 have any questions, please contact us.

Very truly yours, YANKEE ATOMI' ELECTRIC COMPANY l

E D. E. Vande. burgh Senior Vice Pre ident JAK/ dis COMMONWEALTH OF MASSACHUSETTS)

)ss COUNTY OF WORCESTER

)

Then personally appeared before me, D. E. Vandenburgh, who, being duly l

sworn, did state that he is a Senior Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, and that the statements therein are true to the best of his knowledge and belief.

O ^UT A. R. Soucy Notary PuBTic My Commission Expires September 7, 1984 h

e

O ATTACHMENT A Data Necessary for the Staff Calculation of Containment Temperature and Pressure Decay Time l

l

I.

The containment pressure and temperature analysis that defines the service conditions used in electrical equipment qualification was submitted to the staff (then AEC) in Proposed Change No. 96, August 6, 1971. The containment design basis in that analysis considered the entire blowdown of the primary system plus the entire contents of the secondary side of one steam generator. Since Yankee Rowe does not have a containment spray system, containment energy removal is effected by heat transfer through the steel containment shell to the atmosphers. The resulting containment pressure, temperature and sump water temperature response following the event are shown in Figures 1, 2 and 3 respectively. -Further details of the containment analysis are given in Proposed Change No. 96. Stone and Webster Engineering Corporation performed the containment analysis for YAEC utilizing the LOCTIC digital computer program.

With respect to the PC96 containment analysis, the following information is provided:

I.A Containment Net Free Volume A containment net free volume of 860,000 ft3 was used in the analysis.

I.B Passive Heat Sinks

[

l The following heat sinks were used in the analysis:

2 Heat Sink Material Thickness (In)

Area (Ft )e 1.

Containment Paint

.024 49088.

Sphere Carbon Steel 1.0 Paint

.024 2.

Painted Concrete Paint

.024 505.7 Concrete 18.0 3

Painted Concrete Paint

.024 8820 9 Concrete 24.0 4.

Painted Concrete Paint

.024 7196.2 Concrete 54.0 t

5.

Painted Concrete Paint

.024 17278.

Concrete 60.0 6.

Painted Concrete Paint

.024 1730.5 l

Concrete 72.0

  • Total exposed surface area to containront conditions

O The following physical properties were used:

Specific Heat Density Material BTU /HR-FT OF BTU /LB/0F LB/Ft3 Carbon Steel 26.0

.11 490.

Concrete 0.8

.16 145.

Paint 0.125 3

  • Volumetric heat capacity 43.0 BTU /Ft OF I.C Initial Containment Conditions The following initial containment conditions were used:

1.

Temperature

- 100 F 2.

Pressure 16.0 PSIA 3.

Relative Humidity -

18% (680F Dew Point) 1.D Containment Spray System - N/A I.E Fan Cooler System - N/A I.F Other Containment Heat Removal Systems t

As mentioned in I. above, the containment shell acts as a heat exchanger to the atmosphere. The outside air temperature was assumed to be at 2

90 F with a heat transfer coefficient of 2.0 BTU /HR-Ft _oF.

The 2

inside heat transfer coefficient was assumed to be 1.8 BTU /HR-Ft _op, I.C ' Single Failure Assumption

~

The single failure assumed in the analysis was that one train of ECCS pumps failed to start.

I.H Mass and Energy Release Data The analysis of the Yankee Rowe containment pressure and temperature response given in Proposed Change No. 96 was made using the LOCTIC digital computer program (Stone & Webster Engineering Corporation). At that time (August 1970), mass and energy releases to the containment from the primary and secondary sources were internally calculated by the LOCTIC program. The mass and energy release data given in Figures 4 and 5 essentially represent the LOCTIC internally calculated data.

This release data i. based upon the postulated loss-of-coolant from a double-ended rupture of the largest reactor coolant pipe coincident with a similar failure of the secondary side of one steam generator.

II.

The operation of ECCS assumed in the Proposed Change No. 96 containment analysis is depicted in Figures 6 and 7 for the injection and recirculation modes respectively.

The failt re of one train of ECCS pumps has been assumed.

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