ML19296C544
| ML19296C544 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/28/1979 |
| From: | Moody D Maine Yankee |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19296C536 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 WMY-79-151, NUDOCS 8002260630 | |
| Download: ML19296C544 (3) | |
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617-566-9011 t:::::,::ma::aO December 28, 1979 B.3.2.1 1&W 79-151
' United States Nuclear Regulatory Commissien Washington, D. C.
20555 Attention:
Office of Nuclear Reactor Regulation Mr. Harold Denton, Director
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) NUREG 0578 - Lessons Learned Task Force Status Report and Short Term Recommendations dated July, 1979 (c) USNRC Letter to All Operating Nuclear Power Plants dated September 13, 1979 (d) USNBC Letter to All Operating Nuclear Power Plants dated October 30, 1979
Dear Sir:
Subject:
NUREG-0578, Item 2.1.5a - Dedicated H2 Penetrations References (c) and (d), in accordance with recommendations made in reference (a) requested that a description of any design changes and a schedule for the accomplishment of those changes relative to Dedicated H2 Penetrations be provided in accordance with a category "A" i=plementation schedule.
In accordance with that request, the following information is provided.
A single 2" pipe is used to purge hydrogen from thc containment at Maine Yankee. Additional sample connections permit monitoring of hydrogen concentrations in the containment dome, ventilation ring duct, or from the exhaust air duct at the 23'6" elevation.
The penetration is adequately sized for the flow requirements of the purge sys tem.
The penetration is a combined design that is single-failure prc7f of containment isolation in accordance with your position clarification of Oc tober 30, 1979.
The penetration meets the requirements of General Design Criterion 54.
Containment isolation is provided by two valves in series both located outside containment as shown on the attached sketch.
The valves are locked closed manual valves.
Operation of the post-accident purge system is mm.4ually initiated.
The single failure of an automatic valve will not prevent the system from functioning properly, f r~
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United States Nuclear Regulatory Commission December 28, 1979 Attention:
Mr. Harold Denton, Director Page 2 It is Maine Yankee's belief that the existing system meets the intent of the branch position and no modifications are being contecplated.
We trust that this information is satisfactory; however, should additional information be required, please contact us.
Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY
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B.3.2.1 kHY 80-3 January 7, 1980 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Office of Nuclear Reactor Regulation Mr. Harold Denton, Director
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) NUREG-0578-Lessons Learned Task Force Status Report and Short Term Recommendations dated July 1979 (c) USNRC Letter to All Operating Nuclear Power Plants dated September 13, 1979 (d) UNSRC Letter to All Operating Nuclear Power Plants dated October 30, 1979
- 1) ear Sir:
Subjec t:
NUREG-0578, Item 2.1.8a - Post Accident Sampling Capacity The following information is provided in response to the recommendations and requests made in References (b), (c), and (d) relative to Post Accident Sampling Capability at Maine Yankee.
A design and operational review of the capability to obtain reactor coolant and containment atmosphere samples has been completed. Maine Yankee presently has the ability to perform on-line H2 Analysis, but does not have the ability at this time to take containment air samples.
A conceptual Engineering Design Change which outlines the changes which will be required to install an air sampling device has been issued.
Maine Yankee has the capability to perform isotopic analysis once the air sample has been obtained.
Maine Yankee presently has the capability to handle unpressurized and pressurized reactor coolant samples with radioactivity concentrations up O
to several mci /ml, which is three orders of magnitude lower than the NRC 4
sourne term on reactor coolant. Sampling and analytical procedures hre be..g revised according to the above concentration limits.
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U. S. Nuclear Regulatory Commission January 7, 1980 Mr. Harold Denton, Director Page 2 In order to meet NRC requirements relative to reactor coolant sampling capability, Maine Yankee is evaluating several alternatives. One conceptual design includes the provision of a sampling diluation capability which will allow conventional analysis techniques to be used.
Another involves an investigation into the current availability of instrumentation which can provide the required analysis by on-line monitoring. To meet the total requirement, a combination of alternatives may be necessary.
In the evaluation of these concepts, there are a number of items which require resolution before a decision can be made as to which direction should be pursued.
Maine Yankee expects to resolve these it ums in time to implement the necessary modifications by January 1,1981.
Ne trust that this information is satisfactory; however, should additional information be required, please contact us.
Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY
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D. E. Moody Manager of Operations EWJ/sec
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-r~~O B.3.2.1 January 10, 1980 m 80-8 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Office of Nuclear Reactor Regulation Mr. Harold Denton, Director
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) NUREG-0578 - Lessons Learned Task Force Status Report and Short Term Recommendations dated July, 1979 (c) USNRC Letter to All Operating Nuclear Power Plants dated September 13, 1979 (d) USNRC Letter to All Operating Nuclear Power Plants dated October 30, 1979
Dear Str:
Subjec t: NUREG-0578, Item 2._1.9, Reactor Coolant System Venting References (c) and (d) in accordance with the recommendation made in 1 reference (b) relative to item 2.1.9, requested that information concerning the design and operation of reactor coolant system and reactor vessel head vents be provided.
Accordingly, the following information is submitted:
Maine Yankee will install equipment to vent both the reactor vessel head and the pressurizer by January 1,1981.
This equipment will meet the requirements of NUREG-0578 as clarified by your letter of October 30, 1979 Sketch A, attached provides a flow diagram of the proposed system.
The reactor vessel head vent consists of a motor operated valve installed downstream of an existing manual vent valve.
A flow restrictor limits flow rates through the vent path to below the charging system makeup capability. The vessel head vent is piped to the pressurizer quench tank.
The pressurizer vent consists valve, block valve and associated pressurizer quench tank. A ruptu containment. Maine Yankee is pre DUPLICATE DOCUMENT the solenoid operated relief valv determine if it meets, or can be Entire document previously criteria. If this criteria canno entered into system under:
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suitable restriction orifice will No. of pages:
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