Letter Sequence Other |
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Results
Other: 05000267/LER-1982-007, Forwards LER 82-007/01T-0.Detailed Event Analysis Encl, 05000267/LER-1982-007-01, /01T-0:on 820222,control Rod Pairs for Regions 7 & 28 Did Not Insert Automatically Following Manual Scram. Possibly Caused by Binding or Sticking of Control Rod Drive Mechanism.Control Rods Exercised to Eliminate Sticking, 05000267/LER-1984-012-01, :on 841105,reserve Shutdown Hopper of CRD & Orifice Assembly Discharged 40 Lb Reserve Shutdown Matl During Testing.Caused by Formation of Boric Acid Crystals. Absorber Matl to Be Replaced, 05000267/LER-1985-001, :on 850126,scram Occurred on Neutron Flux Rate of Change High from wide-range Channels on Scram Channels a & C.Caused by Welding Machine in Close Proximity to Flux Detectors.Weld Machine Turned Off, ML20084C589, ML20084Q444, ML20092P626, ML20093K194, ML20094D774, ML20096C032, ML20098B305, ML20099K727, ML20100H112, ML20106B531, ML20106B533, ML20112G463, ML20117M059, ML20126B629, ML20127J822, ML20127K637, ML20127L885, ML20127N695, ML20132C948, ML20132E623, ML20132G502, ML20134E865, ML20138Q922, ML20206J841, ML20209E899
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MONTHYEAR05000267/LER-1982-007-01, /01T-0:on 820222,control Rod Pairs for Regions 7 & 28 Did Not Insert Automatically Following Manual Scram. Possibly Caused by Binding or Sticking of Control Rod Drive Mechanism.Control Rods Exercised to Eliminate Sticking1982-03-0808 March 1982 /01T-0:on 820222,control Rod Pairs for Regions 7 & 28 Did Not Insert Automatically Following Manual Scram. Possibly Caused by Binding or Sticking of Control Rod Drive Mechanism.Control Rods Exercised to Eliminate Sticking Project stage: Other 05000267/LER-1982-007, Forwards LER 82-007/01T-0.Detailed Event Analysis Encl1982-03-0808 March 1982 Forwards LER 82-007/01T-0.Detailed Event Analysis Encl Project stage: Other ML20084C5891984-04-16016 April 1984 Provides Advance Notification of Intent to Propose Tech Spec Changes to Circulation speed-high Trip Setting Listed in Table 4.4-3 & Surveillance Requirement SR 5.3.7 for Secondary Coolant Monitoring Project stage: Other ML20084Q4361984-05-10010 May 1984 Application to Amend License DPR-34,revising Tech Specs to Change Circulator speed-high Steam Trip Setting.Change Would Increase Circulator Availability While Providing for Initiation of Protective Actions Project stage: Request ML20084Q4221984-05-10010 May 1984 Forwards Application to Amend License DPR-34,revising Tech Specs to Change Circulator speed-high Steam Trip Setting (Table 4.4-3).Change Would Increase Circulator Availability While Providing for Initiation of Protective Actions Project stage: Request ML20084Q4441984-05-10010 May 1984 Proposed Tech Spec Table 4.4-3, Instrument Operating Requirements for Plant Protective Sys,Circulator Trip. Significant Hazards Considerations Encl Project stage: Other ML20092P6261984-06-26026 June 1984 Confirms Util Commitment to Fully Investigate 840623 Event in Which Six Control Rod Pairs Failed to Insert Into Core Under Automatic Velocity Limited free-fall Sys.Nrc Approval of Resolutions Will Be Obtained Prior to Reactor Startup Project stage: Other ML20090C5261984-07-0606 July 1984 Responds to NRC Concerns Re Fire Protection Review,Bldg 10 Licensing Requirements,Control Rod Failure to Scram, Documentation of Disciplinary Actions,Clearance Tags & Radiological Emergency Exercise Scenario,Per 840625 Meeting Project stage: Meeting ML20094D7741984-07-18018 July 1984 Informs of Control Rod & CRD Insp & Testing in Response to NRC 840709 Insp.Major Power Consumption & Scram Verification of All 37 CRD & Orifice Assemblies Completed & Insp Underway.Plan for Further Action Described Project stage: Other ML20096C0321984-08-21021 August 1984 Provides Findings & Positions Re Investigation of 840623 Failure of Six Control Rods to Automatically Insert Upon Scram.Summary of Work on Four CRDs & Description of Tests Encl.Corrective Actions Listed Project stage: Other ML20098B3051984-09-0707 September 1984 Ro:On 840904,while Removing CRD & Orifice Assembly,Motor Overcurrent Condition on Auxiliary Transfer Cask Shutters Occurred,Preventing Full Closure.Caused by One Control Rod String Not Fully Retracted.Work Temporarily Discontinued Project stage: Other ML20093K1941984-09-24024 September 1984 Submits Info Re Status of Damaged Control Rod Removal on Fuel Deck.Related Info Encl.Possibly Caused by Absorber Strings Not Fully Retracted,Despite Full Retract Limit Switch Indication Project stage: Other ML20099K7271984-11-0808 November 1984 Provides Status of Control Rod Drive & Orificing Assembly (Crdoa) Refurbishing Efforts.Further Investigation of Crdoa Determined That Cause of Inability of Absorber String to Fully Retract Was Cable Failure Project stage: Other ML20112C0491984-12-27027 December 1984 Responds to NRC 841025 Request for Addl Info Re 840510 Application for Amend to License DPR-34,revising Tech Spec Re Helium Circulators Overspeed Trip Setpoint.Analysis Value Encl Project stage: Request ML20112G5061985-01-0404 January 1985 Forwards Status of Planned Audit Response to NRC July 1984 Audit of Plant Operations,Per Denton .Repts Covering Technical Details of Listed Subjs Will Be Provided by 850131,per 841128 & 29 Meetings Project stage: Meeting ML20106B5311985-01-25025 January 1985 Advises That Util Will Perform Turbine Load Rejection from Full Load Test at End of Cycle 4.Tech Spec Amend Will Be Submitted Project stage: Other ML20106B5331985-01-31031 January 1985 Forwards Investigation Into Sources of Chloride in Fort St Vrain Primary Circuit. Rept Re Investigations of Effects of Chlorides on Major Components in Primary Circuit Will Be Sent by 850228 Project stage: Other 05000267/LER-1985-001, :on 850126,scram Occurred on Neutron Flux Rate of Change High from wide-range Channels on Scram Channels a & C.Caused by Welding Machine in Close Proximity to Flux Detectors.Weld Machine Turned Off1985-02-25025 February 1985
- on 850126,scram Occurred on Neutron Flux Rate of Change High from wide-range Channels on Scram Channels a & C.Caused by Welding Machine in Close Proximity to Flux Detectors.Weld Machine Turned Off
Project stage: Other 05000267/LER-1984-012-01, :on 841105,reserve Shutdown Hopper of CRD & Orifice Assembly Discharged 40 Lb Reserve Shutdown Matl During Testing.Caused by Formation of Boric Acid Crystals. Absorber Matl to Be Replaced1985-02-28028 February 1985
- on 841105,reserve Shutdown Hopper of CRD & Orifice Assembly Discharged 40 Lb Reserve Shutdown Matl During Testing.Caused by Formation of Boric Acid Crystals. Absorber Matl to Be Replaced
Project stage: Other ML20132G5021985-03-12012 March 1985 Evaluation of CRD Mechanism & Reserve Shutdown Sys Failures & Pcrv Tendon Degradation Issues Prior to Fort St Vrain Restart Project stage: Other ML20112G4631985-03-18018 March 1985 Forwards Ga Technologies,Inc Rept 907838, Investigation Into Sources of Chloride in Fort St Vrain Primary Circuit, Re Effects of Chloride on Major Components in Primary Circuit.Final Review & Clearance to Be Forwarded by 850326 Project stage: Other ML20100H1121985-03-26026 March 1985 Forwards Evaluation of Fort St Vrain Metallic Components Exposed to Primary Coolant Chloride Contamination, Per 850318 Commitment Project stage: Other ML20117M0591985-04-26026 April 1985 Expresses Appreciation for Opportunity to Discuss Quality Aspects of CRD & Orifice Assembly (Crdoa) Refurbishment Program on 850424 in Arlington,Tx.Discusses 850418 Audit to Confirm 18 Crdoas Completed W/High Quality Project stage: Other ML20132C9781985-05-17017 May 1985 Safety Evaluation Re CRD Instrumentation Project stage: Approval ML20126B6291985-05-20020 May 1985 Responds to Commitment Log Item CL-1055 Re Verification of Operability of Surge Diodes on CRD Brake & Limit Switch Relays.Diodes & Functions Listed.Action Request DCAR-704 Initiated to Provide Relocation of Diodes Project stage: Other ML20127J8221985-06-0707 June 1985 Informs of Acceptability of Devcon 5-minute Epoxy for Use in Cementing Resistance Temp Detector Temp Sensors to CRD Cavity & Motor,Based on Test & Inservice Exposure of Epoxy to High Temps Project stage: Other ML20127K6371985-06-0707 June 1985 Forwards Interim Tech Specs for Control Rods for Use During Plant Startup.Specs Describe Program to Assure Control Rod & Reserve Shutdown Sys Reliability.Operating Limit of 250 F Max on Control Rod Motor Temp Anticipated Project stage: Other ML20127L8851985-06-13013 June 1985 Forwards Results of Engineering Evaluation of Design Changes Introduced in CRD & Orifice Assembly Bearings.Physical Comparison Testing of Original & Replacement Shim Motor Bearings Underway to Establish Operating/Design Margins Project stage: Other ML20127N6951985-06-14014 June 1985 Elaborates on Util Commitments to Listed Plant Activities, Including CRD Mechanism Temp Recording,Requalification, Surveillance & Preventative Maint,Backup Reactor Shutdown Procedure,Tendons & Pcrv Integrity & Electrical Sys Project stage: Other ML20209E8991985-06-25025 June 1985 Discusses Status of CRD & Orificing Assembly (Crdoa) Refurbishment Efforts.First 37 Crdoas Refurbished & Installed.Summary of Design Changes & Test Results Encl Project stage: Other ML20132C9481985-07-0101 July 1985 Evaluation of CRD Orifice Assembly Bearing Rept from Public Svc Co of Co Project stage: Other ML20132E6231985-07-0303 July 1985 Forwards Interim Tech Specs for Reactivity Control Sys.Tech Specs Will Provide Basis for Program to Assure CRD & Reserve Shutdown Sys Reliability.Specs Include Change to Criteria for Insertion of Reserve Shutdown Matl Project stage: Other ML20132C9391985-07-12012 July 1985 Forwards Eg&G 850701 Evaluation of CRD Orifice Assembly Bearing Rept from Public Svc Co of Co, Per Util 850613 Submittal.Installed Bearings Acceptable Replacements for Original Design.Review of 850607 Submittal Also Encl Project stage: Approval ML20134E8651985-07-17017 July 1985 Issue 1 to Procedure SR-TE-9-X, Inserted Rod Position Verification Project stage: Other ML20134E8601985-07-31031 July 1985 Forwards Issue 1 to Procedure SR-TE-9-X, Inserted Rod Position Verification, in Response to Concerns Discussed at 850221 Meeting & in Project stage: Meeting ML20138Q9221985-12-19019 December 1985 Informs of Inability to Meet 851230 Completion Date of High temp,300 F,Crd Mechanism Test & Preliminary Evaluation,Due to Difficulties,Including Orifice Valve on Mechanism.Final Rept Will Be Submitted by 860331 Project stage: Other ML20199D3411986-06-11011 June 1986 Forwards Evaluation of Util Response to 851003 Review of Performance Enhancement Program.Method Should Be Provided to Confirm Functional Acceptability of Equipment Prior to Return to Svc Project stage: Approval ML20206J7481987-04-0606 April 1987 Forwards Amend 52 to License DPR-34 & Safety Evaluation. Amend Increases Circulator speed-high Steam Trip Setting in Table 4.4-3 of Tech Specs Project stage: Approval ML20206J8411987-04-0606 April 1987 Amend 52 to License DPR-34,increasing Circulator speed-high Steam Trip Setting Listed in Table 4.4-3 of Tech Specs Project stage: Other ML20206J9331987-04-0606 April 1987 Safety Evaluation Supporting Amend 52 to License DPR-34 Project stage: Approval ML20206B3301987-04-0606 April 1987 Requests Fr Publication of Notice of Issuance of Amend 52 to License DPR-34,increasing Circular Speed High Steam Trip Setting Listed in Table 4.4-3 of Tech Specs Project stage: Approval 1985-02-28
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Text
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t public service company e onnomde i
16805 WCR 19 1/2, Platteville, Colorado 80651 g
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April 16, 1984 k'
APR 23 G1M l
Fort St. Vrain unit #1 dL$
P-84112 Mr. Phil C. Wagner, Project Manager Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, TX 76011 Docket No. 50-267
SUBJECT:
Intentions for Technical Specification Changes to i
Table 4.4-3 and SR 5.3.7
Dear Mr. Wagner:
This letter is to provide advance notification of Public Service Company's intentions to propose Technical Specification changes to the Circulator Speed-High (steam) trip setting listed in Table 4.4-3 and the Surveillance Requirement, SR 5.3.7, for Secondary Coolant activity monitoring.
Public Service Company will propose that the circulator overspeed trip setting be increased to avoid unwarranted circulator shutdowns in preparation for consistent 100% power operation. The increase in trip setting, 11000 to 11700 rpm (115% to 123% rated), would continue to ensure the initiation of necessary protective actions prior to reaching the postulated maximum credible overspeed condition of 135%
rated or the blade shedding safety limit of 170% rated. This change will be proposed exclusive of the general Section 4.4 Setpoint Reevaluation program proposal due to the anticipated near term benefits at 100% power operation.
8404300123 840416
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PDR ADOCK 05000267 P
PDR
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% The proposed change to SR 5.3.7 would decrease the activity level at which the frequency for sampling and analysis of the secondary coolant must be increased.
Upon reaching a secondary coolant activity level of 10% of the safety limit of LC0 4.3.8 (presently 25%), the frequency of sampling and analysis would be increased from weekly to daily and would continue on a daily basis until the activity levels decrease to less than 10% of LC0 4.3.8.
Public Service Company feels that this requirement is necessary in assuring that secondary coolant activity levels, along with personnel exposure, health physics coverage, and radioactive waste shipments, are kept ALARA.
Public Service Company will also propose that the requirements for increased sampling and analysis frequency when activity levels increase "by a factor of 25% over the previous equilibrium value", be deleted. Due to the very low level of activity normally present in the secondary coolant, 0.01% of the limit of LCO 4.3.8, variations of 25% are considered normal and not indicative of a significant activity increase, which is the intent of this requirement. A single action level at 2 10% of the limit of LC0 4.3.8 is considered adequate to monitor secondary coolant activity and more conservative than the present requirements.
These proposed changes are expected to be submitted following review and approval by the Nuclear Facilities Safety Committee at the next scheduled meeting in May, 1984.
If you have any questions, please contact me at (303) 785-2224.
Very truly yours, d 7TN/
Don Warembourg-Manager, Nuclear Production DWW/djm 4
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