ML19321B245

From kanterella
Jump to navigation Jump to search
Forwards Special T4 Teledyne Valve Operator Performance of Unit in Steam Environ Indicated in Westinghouse Equipment Spec G676258. Rept Updates & Supplements Table A-1 Attached to NRC
ML19321B245
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 07/27/1978
From: Counsil W
CONNECTICUT YANKEE ATOMIC POWER CO.
To: Ziemann D
Office of Nuclear Reactor Regulation
Shared Package
ML19268C980 List:
References
TASK-03-12, TASK-3-12, TASK-RR NUDOCS 8007300338
Download: ML19321B245 (2)


Text

f.,.

CONNECTICUT YANKEE t'

i

(,

BERLIN. C O N N E CTIC U T P.O.BOM 270 M ARTFORD. CON N ECTICUT 06101

/ 'j Tatsenene

(,J July 27, 1978 2os see-east Docket No. 50-213 Director of Nuclear Regulatory Regulation ATTENTION:

Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 U. S. Nuclear Regulatory Commission Washington, D. C.

20555

References:

(1)

D. C. Switzer letter to V. Stello, Jr.,

dated March 6, 1978 (2)

D. L. Ziemann letter to W. G. Counsil, dated June 23, 1978 Gentlemen:

Haddam Neck Plant Environmental Qualification of Electrical Equipment In Reference (2), the NRC Staff requested that CYAPCO supplement Table A-1 in the Attachment to Reference (1) with additional information. As a result J

of follow-up ef forts conducted by CYAPCO and Northeast Utilities Service Company (NUSCO) and, in response to Reference (2), the attached information is provided.

The Attachment updates and supplements Table A-1 with specific information requested by the NRC Staff.

Information regarding the specific equipment types, the specific environmental conditions to which they were qualified, the method of qualification, and references to qualification documentation are provided therein.

As indicated in Reference (2), the referenced documentation is not being submitted but is available for NRC Staff review.

In addition, ef forts are continuing at CYAPC0 and NUSCO to ensure the availability of appropriate documentation of environmental qualification of safety related electrical equipment.

800730033Q

. 2 --

]

We trust this information is responsive to the NRC Staff requcSts.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPAW f., J ()

t

'//'..L]. 24, W. G. Counsil Vice President Attachment l

\\

,e

e ATTACILMENT i

('~-

DOCKET No. 50-213 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT SUPPLEMENT #1 I

l i

l l

i i

r July,1978 i

TABLE A-2 PEAK CONTAINMENT TEMPERATURE

  • l MAIN STEAM LINE BREAK INSIDE CONTAINMENT Containment Contamination Initially At At 1090F,50% R.H.

1200F, 100% R.H.

50% Liquid Inventory In a

S/G After 245.1 0F 251.7 F

~ ?edwater Valve Closes 0

70%

252.0 F 258.4 F i

i 100%

261.3 0F 267.3 0F

  • Using. Conservative S/G Flow Rates and Enthalpies.

{.

_ _ _ _.. _,. - ~ ~, _

~

h..

b h.

h 1

~

TABLE A-3 Realistic Containment Radiation Qualification CriteriaLI J

(RADS)

TOTAL DOSE 1 Hour 24 ilour 30 Days

. Location Ex' posed (2)

Covered (2)

Exposed Covered Exposed _

Covered 1

Reactor Cavity Area 1.3E+6 1.2E46 1.8E+6 1.3E+6 2.9E+6 1.4E+6 2

Refueling Floor Area 3.0E+5 2.2E+5 8.3E+5 3.lE+5 1.9E+6 4,4E+5 3

- Electrical Penetration Area 8.6E44 1.8E+4, 5.9E+5 7.4E+4 1.9E+6 4.5E+5 4

CAR Fan (3) Motor 5.9E+4 6.9E+5 1.6E+6 5

Lower (4) Annulus Region 8.8E+4 1.8E+4 5.9E+5 7.s a 1.9E+6 4.5E+5 6

Upper (5) AnnJ1us 3.lE+6 1.6E+6 Region 1.4E+5 5.9E+4 1.2E+6 6.9E+5 A) Includes 30 year and post LOCA dose.

[

(1)

B) Post LOCA dose assume 2%. Core Inventory Released per NRC Reg. Guide 4.2, Proposed Annex to Appendix D, 10CFR53, Class 8 accident.

(2)

Exposed = Beta + Gamma Dose v Neutron Dose.

Covered = Gammas + Neutron (3)

Includes an additional 10% dose from fan F-17-3 (Stone & Webster conversation of 2/24/78).

(4)

Assuming no doorway exists in inner annulus wall near equipment.

(5)

Assuming equipment is at least as far from the CAR fan filter as the motor.

1:

es REFERENCES (1)

V. Stello letter to D. C. Switzer dated December 23, 1977.

-(2)

D. C. Switzer letter to K. R. Goller dated February 5,1975.

(3)

D. C. Switzer letter to K. R. Goller dated December 18, 1974.

'(4)

.D. C. Ss_czer letter to A. Giambusso dated June 29, 1973.

(5)

D. J. Skovholt letter to D. C. Switzer dated March 29, 1974.

(6)

A. Schwencer letter to D.' C. Switzer dated July 14,19/,.

(7) NRC General Design Criterion 4 - Environmental and missile design bases.

Structures, systema, and components important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents. These structures, systems, and components shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from events and condi-tions outside the nuclear power unit.

(8)

D. C. Switzer letter to P. A. Morris dated December 30, 1971, as supple-mented on May 19, 1972, December 5, 1972, and May 2, 1977.

(9)

D. C. Switzer letter to R. A. Purple dated September 29, 1975.

(10)' A. Schwencer letter to D. C. Switzer dated June 30, 1976.

.(11)

D. C. Switzer letter to A. Schwencer dated February 2, 1978.

(12) ' D. C. Switzer letter to B. H. Grier, dated January 13, 1978.

(13)

D. C. Switzer 1.etters to A. Schwencer, dated February 2 and 10, 1978.

~

(14)

D. C. Switzer letter to E. G. Case dated February 13, 1978.

(15)

D. C. Switzer letter to E. G. Case ~ dated December 12, 1977.

.b

_