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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 ML20083M9351984-04-12012 April 1984 Discusses Problems W/Pcrv Prestressing Sys & Resultant Insp Test Results.Liftoff Tests Show Tendon Sys Operable.Nrc Permission to Return to Power Operation from Present Refueling Outage Requested by 840418 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 ML20084H4571984-04-25025 April 1984 Forwards Relaxation Curves for Prestressed Concrete Reactor Vessel Tendon Sys,In Response to 840419 Request.No Immediate Mechanism for Controlling Sleeve Atmosphere Provided.Areas W/Indicated Corrosion Regreased Project stage: Other ML20084P5941984-05-0707 May 1984 Forwards Pcrv Tendon Sys Relaxation Curves Containing Min Design Lines,Per H Polk 840503 Telcon Request 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 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 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 ML20092D9271984-06-15015 June 1984 Responds to Requesting Details of Proposed Tendon Surveillance Program.Program Consists of Load Cell Data & Visual Insps.Surveillance Started on 840601.Program Developed Using Reg Guide 1.35 as Ref 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 ML20093J1171984-07-20020 July 1984 Forwards Rev 2 to Updated FSAR for Fort St Vrain.Rev Includes Safety Evaluations Either in Support of License Amends or in Support of Conclusions That Changes Did Not Involve Unreviewed Safety Question Project stage: Request ML20094R4001984-08-0909 August 1984 Confirms 840806 Telcon on Tech Spec Change Request Re Tendon Corrosion & Anchor Assembly Surveillance.Tech Spec Change Request Will Be Submitted by 840930 Project stage: Other ML20096C9081984-08-20020 August 1984 Responds to Re Possible Design Mods to Pcrv Tendons & Details of Evaluations & Schedule of Completion of Repts Detailing Results of Metallurgical Exams.Actions Necessary to Evaluate Design Mods for Pcrv Listed 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 ML20107K2301984-10-18018 October 1984 Updates Tendon Investigations & Corrosion Prevention Programs.Efforts Concentrated on Corrosion Prevention Methods Rather than Detailed Moisture Measurements 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 ML20112D7361984-12-14014 December 1984 Forwards Tendon Accessibility Info,Rationale for Tendon Surveillance & Info Re Corrosion Mechanism in Response to 840720 & 1029 Requests for Addl Info.Tendons Considered Acceptable If No Major Mods Necessary 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 ML20106B6131985-01-31031 January 1985 Discusses Visual Insp of Top Longitudinal Tendons,Per 850115 Meeting Request.Visual Insp of 30% of Longitudinal Tendons for Buttonheads Noted.Inconsistency Exists Between Last Mapping of Raised Buttonheads & Current Insp Results Project stage: Meeting ML20106B5791985-01-31031 January 1985 Submits Plans for Implementing Interim Tendon Surveillance Program,In Response to Concerns.Surveillance Program Will Be Based on Proposed Tech Spec SR 5.2.2,submitted in DW Warembourg 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 ML20117M1211985-04-22022 April 1985 Amends 1,080 Amp/H Ref in to 1,058 Amp/H of Required Battery Capacity to Satisfy Load Profile 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 ML20128N2861985-05-20020 May 1985 Informs of Intent to Conduct Addl Insps of Random Sample of Pcrv Bottom Head Longitudinal Tendon Anchor Assemblies. Thirty-four Longitudinal Bottom End Caps Accessible.Ten End Caps Will Be Removed & Inspected Project stage: Other ML20126C5211985-05-23023 May 1985 Discusses Investigation of Methods to Control Tendon Corrosion Involving Establishment of Nitrogen Blanket on Pcrv Tendon Sys.Establishing & Maintaining Overall Nitrogen Blanket Sys for Tendons Highly Questionable Project stage: Other ML20128P6271985-05-23023 May 1985 Summary of 850516 Meeting W/Util Re Emergency Electrical Power Sys Concerns Resulting from Staff Evaluation of Problems from Testing Emergency Diesel Generators on 841218. Justification for Continued Operation Requested Project stage: Meeting ML20133E7491985-05-28028 May 1985 Requests Interim Evaluation Re Acceptability of Automatic & Manual Control of Emergency Electrical Power Sys by 850607, Per 850516 Meeting W/Util.Summary of Meeting Encl.W/O Encl Project stage: Meeting ML20127K1371985-06-0707 June 1985 Discusses Insp of 10 Bottom Longitudinal Tendon End Caps. Tendons Visually & Magnetic Particle Inspected for Evidence of Corrosion,Concavity,Water,Apparent Failures & Cracking.No Raised Buttonheads Found.All Tests Negative 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 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 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 ML20127N6551985-06-14014 June 1985 Responds to Concerns Raised During 850516 Meeting in Bethesda,Md Re Review of Emergency Electric Power Sys. Response Addresses Independence of Redundant Emergency Power Trains,Rapid Transfer Sys Testing & Switchgear Control Sys Project stage: Meeting 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 ML20138A8551985-07-0202 July 1985 Safety Evaluation Accepting Util Tendon Surveillance Proposal.Proposal Will Lead to Maintaining Structural Integrity of Reactor Vessel.Plant Structurally Ready for Restart Project stage: Approval 1984-09-07
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PublicService reuo s..
Company of Colorado June 14, 1985 Fort St. Vrain Unit No. 1 P-85199 Regional Administrator lW@]Q@ %
Region IV y
]
U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000
) '
R N I B 155 Arlington, Texas 76011
?d L..._.
Attention: Mr. Eric H. Johnson
_J Docket No. 50-267
SUBJECT:
Additional Comitment Information
REFERENCES:
(1) NRC Letter, Denton to Walker, dated 10-16-84 (G-84392)
(2) PSC Letter, Lee to Johnson, dated 1-4-85 (P-85003)
(3) NRC Letter, Martin to Lee, 8507020085 850614 dated 1-17-85 (G-85024)
PDR ADOCK 05000267 F
PDR (4) PSC Letter, Lee to Johnson dated 1-28-85 (P-85030)
Dear Mr. Johnson:
References (1) through (4) identify the NRC Assessment Report findings and the various PSC activities and comitments that must be completed in response to the Assessment Report.
Based on recent contacts with the NRC staff, PSC's comitments related to several Fort St. Vrain plant acti"ities require elaboration.
Attachment 1 to this letter consolidates PSC's comitments related to the following areas:
A.
CRDM Temperature Recording and Requalification,
(
(W1 B.
CRDM Surveillance and Preventive Maintenance, f
g C.
Backup Reactor Shutdown Procedure, g
c D.
Tendons and PCRV Integrity, t
7 E.
Electrical Systems, and
[]
)
m
Long Ter.n Issues.
If you have any questions concerning these issues, please contact Mr. M. H. Holmes at (303) 571-8409.
Very truly yours, H. L. Brey, Manager Nuclear Licensing and l
Fuels Division i
/
HLB /MRS/sem l
J t
Page 1 of 4 ADDITIONAL COMMITMENT INFORMATION Note: References for this attachment are listed on page 4.
A.
CRDM Temperature Recording and Requalification Per the interim Fort St. Vrain Technical Specifications for control rods, (reference 1), CRDM motor temperatures will be monitored to insure CRDM motor temperatures are less than 250 degrees Fahrenheit.
In the event CRDM motor temperatures exceed l
215 degrees Fahrenheit, the temperatures will be recorded.
PSC has installed a multipoint recording device which provides frequent monitoring (at least one reading per minute) for each CRDM assembly motor temperature. Presently, PSC has a program underway to requalify CRDM motors for operating temperatures to 300 degrees Fahrenheit, (reference 2).
B.
CRDM Surveillance and Preventive Maintenance l
Current CRDM Surveillance and Preventive Maintenance Programs at l
Fort St. Vrain are described in reference 3.
(
Detailed CRDM curveillances and preventive maintenance l
requirements have been included in the interim Fort St.
Vrain l
Technical Specifications for control rods, (reference 1).
These I
surveillance actions will provide assurance that necessary Rod Position Indicators are operable and accurate.
In addition, PSC is determining the feasibility of developing enhanced surveillance tests and preventive maintenance practices.
This development effort will review CRDM surveillances and maintenance / overhaul experiences and results, and determine whether surveillance activities, schedules, or acceptance criteria can be improved.
PSC's plans for developing enhanced surveillance tests and preventive maintenance practices will be submitted for NRC review within 6 months of plant restart.
Page 2 of 4 C.
Backup Reactor Shutdown Procedure The requirements outlined in reference 1 will be incorporated into appropriate plant operating procedures including the necessary steps to be taken for reserve shutdown system (RSD) actuation. These procedures will require insertion of sufficient RSD material to achieve the required Shutdown Margin within one hour after determination that adequate Shutdown Margin does not
- exist, if the situation cannot be otherwise rectified within the one hour period.
D.
Tendons and PCRV Integrity The current interim Fort St. Vrain revised Tendon Surveillance Program is outlined in reference 4.
This program changes the previously proposed 18 month frequency for visual inspection to a six month frequency. The proposed program also establishes a control group of tendons to permit a aetter assessment of corrosion rate.
Additional inspections consist of examining the tendon end caps, prestressing anchor assembly stressing washer, shims, bearing
- plate, and buttonheads for evidence of general corrosion, concavity, water or other apparent failures.
Recent examination results are described in references 5 and 6.
Liftoff tests measuring the amount of load in the tendons are also being performed as described in reference 7.
PSC will provide the NRC with the results of the interim surveillance program every six months after plant restart.
Additionally, as part of the Technical Specification Upgrade Program, the requirements of the interim Tendon Surveillance Program will be incorporated into the Technical Specifications.
E.
Electrical Systems Reference 8 contains PSC responses to NRC concerns from the recent electrical system review including 1) 4kV Rapid Transfer System, 2)
Independence of Redundant Trains, 3) Testing of the 4kV Rapid Transfer System and 4) Switchgear Powering.
Page 3 of 4 F.
Long Term Issues Reference 9 contains PSC responses to the long term issues identified in the NRC Assessment Report of October 16, 1984.
Some of these issues have been completed, (e.g., CRD motor temperatures and Watt meter testing). The remaining issues are in progress and PSC will submit a schedule for their completion within two months of restart.
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Page 4 of 4 a.
REFERENCES FOR ATTACHMENT 1 1.
PSC Letter, Lee to Johnson, dated 6-7-85 (P-85180) 2.
PSC Letter, Lee to Johnson, dated 1-30-85 (P-85032) 3.
PSC Letter, Lee to Johnson, dated 1-31-85 (P-85040) 4.
PSC Letter, Warembourg to Johnson, dated 3-5-85 (P-85071) 5.
PSC Letter, Warembourg to Johnson, dated 5-20-85 (P-85176) 6.
PSC Letter, Warembourg to Johnson, dated 6-7-85 (P-85193)
- 7. _PSC Letter, Warembourg to Johnson, dated 3-18-85 (P-85084) 8.
PSC Letter, Warembourg to Johnson, dated 6-14-85 (P-85208) 9.
PSC Letter, Lee to Johnson, dated 1-4-85 (P-85003) l
- -_,