Letter Sequence Request |
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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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of Odlendo 16805 WCR 19 1/2, Platteville, Colorado 80651 September 13, 1984 Fort St. Vrain Unit #1 P-84351 G20Ws W
, );
Mr. John T. Collins 1,J Regional Administrator SEP I 8124 U. S. Nuclear Regulatory Commission
,4 611'Ryan Plaza Drive, Suite 1000
~
3 Arli,.gton, Texas 76011 i
ATTN: Mr. Eric H. Johnson
SUBJECT:
PCRV Pressurization Above 100 psia REi-ERENCE:
- 1) PSC Letter, Lee to Johnson, Dated E
8/22/84,(P-84310)
- 2) NRC Letter,- Johnson to Lee, Dated 6/28/84,(G-84215)
Dear Mr.-Col' lins:
The purpose of this letter is to clarify statements that were made in Reference 1) regarding the method that we would employ to enhance moisture' removal should our request for relief from the 100 PSIA PCRV
. pressure res r ct i tion be granted.
The-current restriction of maintaining the PCRV pressure at
. <:100 psia has significantly reduced our capability. for removing remaining moisture from the primary coolant, particularij when it is combined with the low' circulator helium inlet temperatures that now exist.(< 100'F).
When moisture is introduced into the PCRV via the circulator bearing water auxiliary system, it accumulates in the insulation near the affected
. circulator.
The rate of moisture removal from the insulation is dependent on a number of variables, but the two major parameters, are the differential pressure across the circulator inlet to outlet plenums, and, less importantly, the temperature of the' primary coolant.
60- % 7
/
V 1
0 d0 U
f 0409240059 540913 o go PDR ADOCK 05000 ll 0 4
J
,,.. Historically, we_ have determined that. the =best. mechanism for jincreasing the circulator differential pressure is to pressurize the TPCRV and then to. operate the affected circulator at a relatively high speed. This method of operation increases the helium mass flow rate through tne ~~ circulator diffuser, resulting in a higher circulator differential pressure and'an increase in the rate of moisture removal
'fromo the' insulation.
It also results in a larger-helium mass flow trate through the purification system.
-The above method can Lbe somewhat. enhanced, by-increasing the temperature of.the primary coolant..In order to accomplish this, auxiliary boiler steam is admitted to the reheat section of the steam generator (s) to heat the primary coolant as it passes over the steam
. generator. tubing.
. Typical.PCRV pressures. and primary. coolant temperatures are in the 150-300: psia' and.250-400*F ranges under the described moisture
. removal._ effort. Obviously, the exact pressures and temperatures are dependent,on a number of. plant conditions which may exist at _the time.
As always, the Fort St. Vrain Technical Specifications will govern our-activities..We will, of course, maintain the reactor in_a shutdown condition until released to startup by the NRC.
Since -restricting the. PCRV pressure to < 100 psia is in no way related to: the control rod-drive _ situation currently under investigation,' and.since continued high moisture levels in the PCRV
.are not desirable, we request relief from the 100 psia PCRV pressure restriction' imposed by Reference 2).
- 1. I f you have~ any' questions, please contact Mr. Chuck Fuller of my staff at (303) 785-2224.
Sincerely,-
J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear-Generating Station
_ JWG/djc-b