ML20132A799
| ML20132A799 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/15/1979 |
| From: | Moody D VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| WVY-79-69, NUDOCS 7908200419 | |
| Download: ML20132A799 (4) | |
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VER510NT YAN KEEiNUCLEAR POWER CORPO1 NATION
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ENGINEERING OFFICE TURMPtsCrROAo WESTBOR O. M AssAcHUS ETTS 01 S e t vau w==..:.+....
j VVY 79-69 Jun's 15, 1979 l
United States Nuclear Regulatory Coonission Of fice of Inspection and Enforcement Region I 3y 631 Park Avenue
.i King of Prussia. Pennsylvania 19406 Attention: Boyc3 N. Criar, Director
References:
(1)
License NoJ'DFE-28 (Dockit No. 50-271)
(2)
IE Bulletia No; 79-01 F ;-
(3)
YTMFC !atter to USIRC, No,' EV1-37, dated April 4,19791;m e
(4)
VTEPC Latter to DSlac, No. UYY-45, dated ' April 24, 1979 (G
Dear Sir:
subject:
Enviroissental Qualification of Class 1E Equipment Reference (2) required action to be takan on providing written evidence of the qualification *of electrical equipment required to function under accident conditions at Vermont Tankaa. In compliance with this requirement, we are providing the following responses.
l 1.
_Inside Contalment The envirousental qualifications of electrical equipoent located inside the primary reactor containment and steen tunnel which are required to remain operable during and/or subsequent to a Design Basis Accident (DBA) have been reviewed for adequacy. This information is provided in YAEC Report 1179A "Sunnary:
Environnental Qualification of Safety Related Electrical Equipment Within the Primary Containment and Steam Tunnel at Vermont Yankee Nuclear Power Station" which is enclosed as Attachment 1.
l II. Outside Contairveent A.. The only ares subject to abnormal environments outside the primary contat::sent has been identified as the Rasctor Building (Secondary 7908200
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t U.S. Nuclear Regulatory Commission June 15, 1979
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Atta: Office of Inspection and Ehforcement Page 2 i
i containment).
i ne enviromental conditions la the Reactor Railding as a result of a i
postulated accident in the primary containment or stem tonel are given j
below. These conditions have been established la FSAR Question / Answer No. 7 7.
Reactor Buildina Post-Accident Environsental Conditions 8
Temperature 150.
Pressure 0 25 pois Relative >=uity 901 Radiation - Maximum Dose Rate 350 R/hr Integrated dose -12 hr 4200 R 2 day 1.
x 10' E 30 day 1
1 180 day 1
1 8.
All the equipment in the reactor building which is required to function under the above postulated envirosusental coor.itions have been identified.
This equipment includes the foll:nring categoriass 1.
Support electrical systems used to operate equipment located within the primary containment and/or steam taael which are required to faction during a postulated accident 2.
Various valves 3.
Post accident monitoring instrumentation C.
The electrical componesta that are part of this equipment are given below:
1.
Motors required for
- a. Besidual Beat Removal Service Water Pumps
- b. Residual Heat Removal Pue is
- c. Standby Liquid Contro'. Pumps
- d. Core Spray Pumps
- e. Standby Cas Treatment Exhaust Fan
- f. High Pressure Coolant Injection System Auxiliary 011 Pump
- 3. Containment Air Dilution System
- h. Miscellaneous Limitorque Valve Operators 2.
Various cables as required for the above equipment 3.
Uninterruptible Power System as a power supply for certain ECCS valves
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1 U.S. Nuclear Regulatory Commission June 15, 1979 l
F Atto: Office of Inspectica and Enforcement Page 3
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Motor Control Centers for the above listed motors 5.
Post Accident Monitoring System Transmitters III. Conclusions References (3) and (4) identify certain stem mounted limit switches (NAMCD Type EA740, 86700) as le M a=_ adequate environmental qualification.
Although not required for the accident situation, these switches are scheduled to be replaced with qualified switches at the next scheduled
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shutdown following receipt of qualified switches.
In addition, our investigations have revealed that the following items lack sufficient dacumentation for an adequate review of their qualifications. 14 ile we have some indication that they are suitable for operation in their postulated environments, no concreta evidence verifying i
this fact has been obtainableg at the same time we have come across no evidence stating that they are unqualified.
(1)
ASCO DC Solenoids (Modal #UPET830364F) used for the Main Steam Ralief Valves EV-2-71A, 3, C, D.
(2)
ASCO AC-DC-Solenoids used for inboard Main Steam Isolation Valves A0-V-2-80A, S. C, D and the outboard Main Steam Isolation Valves A0-Y-2-86A, B, C, D.
(3)
Thermo Electric Thermocouple (Caramo-Frenium Grade Model CaS16-2-516) used for Primary Containneet Atmospheric Temperature Monitoring System, thermocouple number TE-16-19-30.
(4)
ASCO Solenoid (Model 8315C22) used for the teactor Sampling Flow Control Valve FCV-2-39.
(5) ove'rload relays in MCC 85 and 95 for Standby Liquid Control Punps F-45-12 and P45-1A.
We are continuing our efforts to obtain further information on qualification of this equipment, and are hopeful that this can be obtained in the near future. If, however, no satisfactory qualification data is obtained, within the next three sonths, we vill commit to replace this equipment at the next scheduled shutdown following receipt of equipnent with adequate qualification documentation. We believe that continued operation is justified because the equipment has not been proven to be unqualified. If replacement becomes necessary, this vill be done as a precautionary measure. Ibrthermore, our records to date have shown no signs of deterioration of this equipment.
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1 U.S. Nuclear Regulatory Commission June 15, 1979 Atta Office of Inspection and Enforcenest Page 4 Reference (5) requires that information be provided concerning ASCO
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solenoid valves used in safety-related systems at Vermont Yankee. We believe l
that we have inswered these concerns in our above responses to Reference (2). In addition, a preventive maintenance program will be conducted in.
accordance with the requirements of this bulletin (Ref (5)).
We trust that this information is satisfactory; however, should l
you have any further que'stions, please contact us.
Yery truly yours, TEIMONT YANKEE NUd, LEAR POWER CORPORATION i
W D
E. Noody Manager of Operations 1
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