Letter Sequence Approval |
---|
|
Results
Other: ML20083M935, ML20084H457, ML20084P594, ML20092D927, ML20094R400, ML20096C908, ML20106B579, ML20107K230, ML20112D736, ML20126C521, ML20127K137, ML20127N695, ML20128N286, ML20132G502, ML20154A542, ML20235N112
|
MONTHYEARML20083M9351984-04-12012 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 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 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 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 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 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 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 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 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 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 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 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 ML20138A8071985-07-0202 July 1985 Forwards Updated Safety Evaluation Accepting Util Commitments Re Tendon Surveillance as Basis for Restart. Util Will Incorporate Modified Tendon Surveillance Program Into Tech Specs & Provide Results 6 Months After Restart Project stage: Approval ML20132G4501985-07-0808 July 1985 Forwards Safety Evaluation Re Pcrv Prestressing Tendon Wire Corrosion Problems.Submittals & 0614 Acceptably Resolve Concerns.Lasl Evaluation Rept Encl Project stage: Approval ML20132G4761985-07-0808 July 1985 Safety Evaluation Re Pcrv Tendon Corrosion Investigation & Proposed Remedy.Tendon Surveillance Proposal Acceptable Project stage: Approval ML20235N1121987-07-0909 July 1987 Forwards Lasl Technical Evaluation Rept, Technical Assistance for Fort St Vrain Task Ii:Pcrv & Pcrv Tendon Evaluation, Final Rept Project stage: Other ML20154A5421988-08-30030 August 1988 Requests Addl Info Re Rev 7 to Schedule Commitment Items on Pcrv Tendon Surveillance Involving Provision of Schedule for Conducting Evaluation within 45 Days for Pcrv Tendon Degradation Project stage: Other 1985-01-31
[Table View] |
|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20246J3261989-08-30030 August 1989 Safety Evaluation Supporting Amend 72 to License DPR-34 ML20245J3781989-08-14014 August 1989 Safety Evaluation Supporting Amend 71 to License DPR-34 ML20245J4511989-08-0808 August 1989 Safety Evaluation Responding to Issues Re Tech Spec Upgrade & Plant Defueling.Stated Tech Spec Sections Should Be Upgraded ML20246J3131989-07-0707 July 1989 Safety Evaluation Concluding That Operators Role in Mitigating High Energy Line Break at Facility Acceptable ML20247R2261989-05-26026 May 1989 Final Safety Evaluation Re LER 87-20 Concerning Interactions Between Steamline Rupture Detection/Isolation Sys,Plant Protective Sys & Control Sys at Facility ML20245C5031989-04-18018 April 1989 Safety Evaluation Supporting Amend 70 to License DPR-34 ML20248D6501989-03-31031 March 1989 Safety Evaluation Supporting Amend 69 to License DPR-34 ML20236A1401989-02-27027 February 1989 Safety Evaluation Supporting Amend 68 to License DPR-34 ML20235T4511989-02-24024 February 1989 Safety Evaluation Re Facility Core Support Flow Vent Sys. Continued Operation of Facility W/Current Core Support Flow Sys Configuration Acceptable ML20235J3421989-02-16016 February 1989 Safety Evaluation Supporting Util Action in Response to Generic Ltr 83-28,item 2.1 (Part 2) Confirming Establishment of Interface W/Either NSSS Vendor or Vendors of Each Component in Reactor Trip Sys ML20235J3841989-02-13013 February 1989 Safety Evaluation Concluding That Continued Operation of Facility Not Affected by Steam Generator Tube Failures Experienced by Advanced gas-cooled Reactors ML20195D3911988-10-27027 October 1988 Safety Evaluation Supporting Corrective Actions of LER 86-017 ML20205G0021988-10-24024 October 1988 Safety Evaluation Supporting Amend 65 to License DPR-34 ML20154J8021988-09-15015 September 1988 Safety Evaluation Supporting Amend 64 to License DPR-34 ML20154J4621988-09-15015 September 1988 Safety Evaluation Supporting Amend 63 to License DPR-34 ML20207F0571988-08-10010 August 1988 Safety Evaluation Supporting Util 870206 Submittal Re Safe Shutdowns During Postulated Accident Conditions ML20207F0431988-08-0505 August 1988 Safety Evaluation Supporting Amend 61 to License DPR-34 ML20207F2411988-08-0505 August 1988 Safety Evaluation Supporting Amend 62 to License DPR-34 ML20151M1601988-07-21021 July 1988 Safety Evaluating Supporting Requirements for Redundancy in Responding to Rapid Depressurization Accident ML20151A9961988-06-20020 June 1988 Safety Evaluation Supporting Amend 60 to License DPR-34 ML20195K0651988-06-15015 June 1988 SER Concurring W/Util Proposed Corrective Actions in Engineering Rept Entitled, Rept of Helium Circulator S/N 2101 Damage & Inlet Piping S/N 2001 Repair & Mod Activities ML20195F9661988-06-15015 June 1988 Safety Evaluation Re Destructive Exam Rept for Fuel Test Assembly-2.Fuel Represented by Fuel Test Assembly-2 Predicted to Be Safe for Operation in Facility for 1,800 EFPDs ML20154F8891988-05-10010 May 1988 Safety Evaluation Re Proposed Safe Shutdown Sys & Exemption Requests Concerning 10CFR50,App R.Licensee Request for Exemptions in Listed Areas Should Be Granted.Concept for Providing post-fire Shutdown Acceptable ML20148S6031988-04-0707 April 1988 Safety Evaluation Supporting Amend 59 to License DPR-34 ML20151B6651988-04-0101 April 1988 Supplemental Safety Evaluation Supporting Util Compliance w/10CFR50.App R Re Safe Shutdown DHR Capacity ML20150C4541988-03-10010 March 1988 Safety Evaluation Concluding That Seismic Analysis Methods for Bldg 10 & Walkover Structure Conservative.Gaps Provided Adequate to Accommodate Relative Motions Which Occur Between Subj Structures & Walkover Structure & Turbine Bldg ML20147C8181988-02-25025 February 1988 Safety Evaluation Supporting Changes to Interim Tech Specs 3/4.1.7, Reactivity Change W/Temp NUREG-1220, Safety Evaluation Accepting Plant Special Senior Licensed Fuel Handler Initial & Requalification Operator Training Program,Per NUREG-1220, Training Review Criteria & Procedures1988-01-13013 January 1988 Safety Evaluation Accepting Plant Special Senior Licensed Fuel Handler Initial & Requalification Operator Training Program,Per NUREG-1220, Training Review Criteria & Procedures ML20237D7631987-12-18018 December 1987 Safety Evaluation Updating 861118 Fire Protection Sys Safety Evaluation.Util Alternate Fire Protection Configuration Acceptable ML20149E1621987-12-18018 December 1987 Marked-up Safety Evaluation Re Proposed Safe Shutdown Sys & Exemption Requests Concerning 10CFR50,App R ML20236U6961987-11-23023 November 1987 Safety Evaluation Supporting Amend 57 to License DPR-34. Addendum to Review of Proposed Tech Spec Change:Core Inlet Valves/Min Helium Flow & Max Core Region Temp Rise,Limiting Condition for Operation..., Technical Evaluation Rept Encl ML20236U5761987-11-20020 November 1987 Safety Evaluation Re Helium Circulator S/N C-2101 Damage. Util Corrective Action Program Initiated ML20236R3001987-11-13013 November 1987 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20238C7621987-09-0202 September 1987 Safety Evaluation Concurring W/Util 870702 & 27 Ltrs & 870818 Telcon Re Elimination or Reduction of Maint Requirements on Certain Fire Seals ML20235N6491987-07-13013 July 1987 Safety Evaluation Supporting Amend 56 to License DPR-34 ML20235F5281987-07-0202 July 1987 Safety Evaluation Re Safe Shutdown of Steam Generator Matls. Under Severe Transient Conditions,Fuel Temp Can Be Maintained Under Accepted Temp Limits & Plant Can Be Safely Shutdown ML20235F5151987-07-0202 July 1987 Safety Evaluation Re Safe Emergency Shutdown of Reactor Sys. Operation at 82% Acceptable ML20235F5441987-07-0202 July 1987 Safety Evaluation Re Effect of Firewater Cooldown on Steam Generator Structural Integrity.All Tests Acceptable ML20235E5281987-06-29029 June 1987 Safety Evaluation Supporting Amend 55 to License DPR-34 ML20216G9511987-06-24024 June 1987 Revised Safety Evaluation Re Steam Line Rupture Detection & Isolation Sys (Slrdis).Slrdis Meets Requirements of 10CFR50, App A,Gdc 20 & GDC 4 ML20216G9911987-06-24024 June 1987 Supplemental Safety Evaluation Supporting Application for Amend to License DPR-34 Re Tech Specs for Steam Line Rupture Detection & Isolation Sys ML20215J5401987-06-22022 June 1987 Draft Safety Evaluation Re Safe Emergency Shutdowns.Facility Operation at 82% Power Acceptable 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 ML20214M4681987-05-20020 May 1987 Safety Evaluation Supporting Amend 54 to License DPR-34 ML20215J8271987-05-0505 May 1987 Safety Evaluation Supporting Amend 53 to License DPR-34 ML20209D7561987-04-22022 April 1987 Safety Evaluation Supporting Util 870211 Submittal Re Performance Enhancement Program,Finding 4-10 ML20206J9331987-04-0606 April 1987 Safety Evaluation Supporting Amend 52 to License DPR-34 ML20205S1141987-03-31031 March 1987 Safety Evaluation Accepting Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing. Facility Designed to Permit on-line Functional Testing,Including Testing of Reactor Trip Contactors 1997-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997 Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co ML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112J6861996-05-31031 May 1996 June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531 ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20097E3201996-01-31031 January 1996 Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation ML20095K4131995-12-26026 December 1995 Rev 3 to Decommissioning Plan ML20095H7211995-12-20020 December 1995 Revs to Fort St Vrain Decommissioning Fire Protection Plan Update ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20096C1671995-12-13013 December 1995 Rev 4 to Decommissioning Fire Protection Plan ML20094M1651995-11-30030 November 1995 Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation ML20092F3461995-09-14014 September 1995 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/ ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20029C6031993-12-31031 December 1993 1993 Annual Rept Public Svc Co of Colorado. W/940405 Ltr ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning. ML20045A4291993-06-0303 June 1993 LER 93-003-00:on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well operator.W/930603 Ltr ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20127F5691992-11-0303 November 1992 Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34 ML20101E5761992-05-31031 May 1992 Monthly Defueling Operations Rept for May 1992 for Fort St Vrain ML20096E8221992-04-30030 April 1992 Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/ ML20095E9601992-04-17017 April 1992 Rev to Fort St Vrain Proposed Decommissioning Plan ML20100R7431992-03-31031 March 1992 Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/ ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 ML20092D0081992-01-31031 January 1992 Monthly Operating Rept for Jan 1992 for Fort St Vrain Nuclear Generating Station ML20102B2241992-01-22022 January 1992 Fort St Vrain Station Annual Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59, for Period 910123-920122 ML20094N6701991-12-31031 December 1991 Public Svc Co Annual Financial Rept for 1991 ML20091J6251991-12-31031 December 1991 Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/ ML20094D6711991-11-30030 November 1991 Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1 ML20090M1871991-11-20020 November 1991 FOSAVEX-91 Scenario for 1991 Plant Exercise of Defueling Emergency Response Plan ML20086D6891991-11-15015 November 1991 Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20085N1451991-11-0505 November 1991 Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available ML20086C5451991-10-31031 October 1991 Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/ ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20085D9861991-09-30030 September 1991 Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/ 1997-07-01
[Table view] |
Text
%
.U
[ [b e T f
UNITED STATES NUCLEAR REGULATORY COMMISSION i
O %, ,R f %vj WASHING TON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN ,
DOCKET NO. 50-267 PCRV TENDON CORROSION INVESTIGATION AND PROPOSED REMEDY PCRV Tendon Degradation -
Background:
In 1984 during the scheduled PCRV tendon surveillance, the licensee discovered that certain PCRV tendons had broken and corroded wires. In order to determine the extent of this problem, the licensee increased the number of visual examinations of accessible tendons ends. He also performed a number of lift-off tests. Metallurgical examinations of the tendon wires and tests on the protective grease that were performed by the licensee indicate that the corrosion is the result of microbiological attack on the original tendon grease. The licensee has proposed to halt this degradation by filling the tendon sheaths with an inert nitrogen " blanket".
As a mechanism for monitoring the condition of the tendons, the licensee has proposed a surveillance program that increases the frequency of the visual inspection and lift-off tests. The surveillance program would O co Pere aa uncorroded tendoa control 9eouP with a corroded teadons scouP to establish the effectiveness of the corrosion arresting method and the trend in the tendon wire degradation. The program would include samples of the longitudinal, circumferential, and crosshead tendons proportional to the population of the tendon types.
Evaluation:
- 1. Monitoring:
The staff evaluated the licensee's proposed program for monitoring the PCRV tendons and finds the proposal acceptable for assuring PCRV integrity in the near term with certain modifications, as discussed below:
The surveillance program, as proposed, would produce a sample of significant size to indicate the trend of the tendon wire degradation and the effectiveness of the corrosion arresting method. However, the information gathered by the licensee from the past and future surveillance activities should be integrated into a complete visual presentation covering all tendons. The purpose of this presentation format would be to provide better information of the extent and significance of the tendon degradation problem. The licensee has committed to incorporate the modified tendon surveillance requirements into the technical specifications.
O e510110109 850702 7 ADOCK 050 gDR
l 1
s . l 4
0 -'-
- 2. Corrosion Control:
The staff evaluated the integrity of the PCRV with the degraded tendons in a safety evaluation dated May 16, 1984. The staff findings were that the reactor vessel was capable of withstanding the operating pressures with the degraded tendons as determined at that time. Since May 1984, a few additional wires have broken but the reactor vessel remains able to adequately withstand the operating pressure. The licensee plans to use a nitrogen " blanket" in the tendon sheaths to halt the degradation of tendons; however, our earlier evaluation indicated concern with this approach. Accordingly, we recommend that the licensee carefully evaluate the effectiveness of other techniques, in terms of their ability to remove oxygen and moisture, and their long tenn effects on tendon corrosion.
- 3. Corrosion Problems at Other Plants:
The corrosion problem at Fort St. Vrain (FSV) appears to be different from the tendon problems recently experienced at some other nuclear plants. In the other plants, tendons are.used in the containment structure which experiences ambient temperatures and the tendon sheaths are filled with grease. The tendons at Fort St. Vrain are located in the reinforced concrete reactor vessel. These FSV tendons experience O higher temperatures than other plants and are in sheaths not filled with grease. The FSV tendon wires themselves are protected by a grease coating and the tendon sheath annulus is coated on the inside with a layer of grease.
A failure mechanism has been identified at the other plants related to stress corrosion cracking of the tendon wire stress washers when water was present, predominately in the lower end of the vertical tendons. The stress washers are manufactured from a high strength steel which is susceptible to stress corrosion cracking when exposed to a source of hydrogen.
The tendon wires at FSV appear to be corroding from the attack of formic and acetic acids generated from microbilogical sources. The corrosion and failures seen to date at FSV seem to be limited to the i wires themselves with only one incident of corrosion occurring on the stress washer. No evidence of failure of the stress washers has been detected to date. The licensee has visually examined 10 of the 34 accessible bottom stress washers of the longitudinal tendons and reported the results in a letter dated June 7,1985. No evidence of cracking was found. However, the possibility of stress washers failing from corrosion cannot be ruled out. The continued presence of moisture in the tendon tubes could lead to failure of the stress washers as seen at other plants. The licensee has proposed an intensified surveillance program which consists of visual inspection of the anchorages and lift-off tests. The licensee proposed to O incorporate these inspection requirements into the plant technical l
s 4
specifications under Section 3/4.6.4 "PCRV Integrity". This intensified surveillance program will require a visual inspection. and a report on a sample of 56 tendons at six month intervals. The surveillance program will also require 37 tendons to be lifted-off their shims to determine the amount of prestress available. A . sample of 12 tendons are designated as a control set for visual inspection and 8 tendons are the control set for lift-off tests. The samples of 44 visual inspection and 25 lift off tendons will be rotated thru the tendon population.
- 4. Restart and Re-evaluation:
The staff has reviewed the licensee's proposed surveillance and the connitment to incorporate the surveillance requirements into the technical specification. The staff accepts the tendon surveillance proposal and find that the proposal would lead to maintaining the structural integrity of the reactor vessel. The staff also finds that the visual inspection of the tendon wire anchorage washer is currently sufficient to determine if failure of the washers has occurred. The increased tendon surveillance would be sufficient to show any tendency of the stress washers to fail similar to those at another nuclear plant. The staff finds the plant structurally ready for restart.
O Principal Contributor:
H. Polk, DE Date: July 2, 1985 m