Letter Sequence Other |
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Results
Other: ML20099C963, ML20106B611, ML20112G495, ML20112G517, ML20133E335, ML20135G405, ML20141P237, ML20155G018, ML20212R258, ML20215J636, ML20216J199
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MONTHYEARML20097J8491984-09-13013 September 1984 Clarifies Re Method to Be Used to Enhance Moisture Removal If Request for Relief from 100 Psia Pcrv Pressure Restriction Granted.Helium Mass Flow Rate Through Circulator Differential Pressure Increased Project stage: Request ML20099C9631984-10-29029 October 1984 Ro:On 840911,moisture Discovered in Purified Helium Supply Line Wells During Installation of New Moisture Sensing Probes.Tests Indicate Leak Source Is Circulator Penetration A.Rate of Leak Approx .05 Gpm Project stage: Other ML20106B6111985-01-24024 January 1985 Informs That Concern W/Seriousness of Moisture Ingress Events & Other Impediments to Obtaining Realistic Plant Operation Prompted Corporate Mgt to Form Improvement Committee Under Chairmanship of Rf Walker Project stage: Other ML20112G5171985-01-24024 January 1985 Responds to HR Denton Identifying Requirement for Development of Plan to Implement Mods Recommended by Moisture Ingress Committee.Improvement Committee Formed to Evaluate Innovative & Substantial Plant Mods Project stage: Other ML20112G4951985-03-12012 March 1985 Responds to 850220-22 Requests for Addl Info Re Improvement Committee & Plant Mods Concerning Reduction of Primary Sys Moisture.Historical Background,Review Committee Responsibilities & Description of Helium Issues Encl Project stage: Other ML20135G4051985-09-0404 September 1985 Notifies of Mod to Helium Circulator Auxiliary Sys to Mitigate Pcrv Moisture Ingress.Digital Test Valve Removed from Main Drain Sys & Will Not Be Reinstalled Project stage: Other ML20133E3351985-09-20020 September 1985 Notifies of Change to One of Mods Provided in Re Helium Circulator Auxiliary Sys.Mod Designed to Mitigate Pcrv Moisture Ingress.Thermal Dispersion Type Flow Elements Removed for Evaluation by Manufacturer Project stage: Other ML20141P2311986-03-14014 March 1986 Forwards SER Re Util 860312 Plans for Mods to Facility in Order to Reduce Moisture Ingress Into Reactor Vessel.Design Mods Should Reduce Likelihood of Moisture Ingress Project stage: Approval ML20141P2371986-03-14014 March 1986 SER Re Util 860312 Plans for Mods to Facility in Order to Reduce Moisture Ingress Into Reactor Vessel.Design Mods Should Reduce Likelihood of Moisture Ingress.Licensee Committed to Conduct Further Studies If Ingress Continues Project stage: Other ML20155G0181986-04-0202 April 1986 Forwards Info Re Fort St Vrain Improvement Committee & Actions Taken & Under Consideration to Mitigate Moisture Ingress Into Primary Coolant Sys,Per Util 850312 Commitment Project stage: Other ML20216J1991987-02-0404 February 1987 Evaluation of Long-Term Effects of Moisture Ingress in Fort St Vrain Nuclear Reactor Project stage: Other ML20212R2581987-04-16016 April 1987 Provides NRC W/Annual Report of Actions Taken by Util or Under Consideration by Util to Mitigate Moisture Ingress Into Primary Coolant Sys,Per Item Iv.A of Encl to Project stage: Other ML20215J6361987-06-16016 June 1987 Forwards Advanced Science & Technology Assocs,Inc Rept Re Moisture Ingress at Facility.Agrees W/Subcontractor,Lasl, Conclusions Re Effects of Moisture Inleakage Occurrences Into Prestressed Concrete Reactor Vessel.W/O Encl Project stage: Other ML20216J1921987-06-17017 June 1987 Safety Evaluation Re Mods to Reduce Moisture Ingress Into Reactor Vessel.Periodic Insps & Preventive Maint Should Be Performed on Pertinent Components.Operational Performance Should Be Continuously Upgraded Project stage: Approval ML20216J1841987-06-17017 June 1987 Forwards Safety Evaluation & Rept Re Mods to Reduce Moisture Ingress Into Reactor Vessel.Lasl Recommends Operational Performance Be Upgraded & Reliability of Power Distribution Sys Be Improved to Reduce Frequency of Moisture Ingress Project stage: Approval 1985-09-04
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public Service Company N CoHolmde f
16805 WCR 19 1/2, Platteville, Colorado 80651
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I October-29, 1984 Fort St. Vrain NOV - 51984 unit i p
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Mr. John T. Collins Regional Administrator U. S. Nuclear Regulatory Commission j
611.Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
HELIUM CIRCULATOR INTERSPACE MOISTURE INVESTIGATION
Dear Mr. Hackney:
On September 11, 1984, new moisture sensing probes were installed in all four purified helium supply line wells to the helium circulators' interspaces.
As the installation was being performed moisture was noticed in the supply line wells.
In order to determine the source of water and the leakage rate, a series of tests were performed on September 22, 1984 through September 28, 1984.
The testing involved draining "A"
and "B" circulator interspaces individually with each corresponding helium circulator operating, self turbining and completely isolated from all sources of water.
In order to determine the rate of moisture ingress into each helium circulator interspace, the interspace was drained over a specified period of time yielding a flow rate.
These tests were performed several times to substantiate the results collected on the previous tests.
In addition, a primary seal leak test was conducted on "A" Helium Circulator's interspace. This was accomplished by -placing a water manometer on the moisture element well of the purified helium supply line of "A" Circulator.
The reactor was then depressurized to 24 inches of water vacuum.
There was no vacuum observed in this interspace, indicating that there is not a primary seal leak.
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From' the testingLperformed, it is apparent that'a bearing water !1eak' of approximately 0.05 gpm exists.inf;the "A" Circulatori penetration.
Due'to the inaccessibility of the-piping within*the-penetration under current ' plant conditions,.the location of the leak cannot be-positively.identif.ied.
=However, there are,a number of-fittings and flanges 'in the' bearing.waterispiping, and it is (likely. that the leak
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..ni((; "L affect the circulator's-operability.
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We will be replacing the "A" Circulator during:the present plant
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[J.--W.Gahm Manager Nuclear Production-3 Fort St. Vrain Nuclear Generating Station 1
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