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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217L8831999-10-21021 October 1999 Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification ML20199K6991999-01-20020 January 1999 Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable ML20199L5951999-01-14014 January 1999 Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i) ML20195C4161998-11-0909 November 1998 SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds ML20155B6471998-10-26026 October 1998 Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage ML20154B6951998-10-0101 October 1998 SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station ML20239A1361998-09-0202 September 1998 SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program ML20216F1001998-04-15015 April 1998 Safety Evaluation Accepting 980331 Licensee Proposal to Perform Alternative Testing for Containment Pressurization Test for Vynp ML20217F3421998-03-25025 March 1998 SER Accepting Plans for 1998 & 1999 Refueling Outages Re Reactor Vessel Internals for Plant ML20212H1521998-03-0606 March 1998 Correction to Page 7 of SE Re Relief Request for Third 10-yr Interval Pump & Valve IST Program for Plant ML20217N4911998-02-27027 February 1998 SER Pertaining to Cracking of EDG Lube Oil Piping at Vermont Yankee ML20198P9941998-01-15015 January 1998 SE Authorizing Relief Requests for Third Interval Pump & Valve Inservice Testing Program ML20141A4151997-06-18018 June 1997 Revised SE Accepting Proposed Onsite Disposal of Slightly Contaminated Silt Removed from Vermont Yankee Cooling Towers ML20135E5401997-03-0303 March 1997 Safety Assessment Accepting Mod of RHR & CS Sys Containment Isolation Function Configuration ML20134N8271996-11-20020 November 1996 Safety Evaluation Accepting Licensee Scope & Insp Methods Proposed for Insp of Core Spray Internal Piping During Fall 1996 Refueling Outage at Plant ML20134F9631996-11-0505 November 1996 Safety Evaluation Re Power/Flow Exclusion Region Calculation Method Using LAPUR5 Computer Code & Implementation of Solomon Stability Monitor for Licensee Facility ML20128N3531996-10-11011 October 1996 Safety Evaluation Accepting Licensee Flaw Evaluation of Indication Found During Reactor Pressure Vessel Insp at Plant ML20129G3611996-10-0202 October 1996 Safety Evaluation Accepting Proposed Repair for Plant Core Shroud ML20057A6991993-09-0303 September 1993 Safety Evaluation of IST Program Relief Requests for Pumps & Valves for Third 10-yr Insp Interval ML20057A2791993-08-12012 August 1993 Safety Evaluation Accepting Licensee Reasons Given for Delay in Completing short-term Actions Requested in Ieb 93-003, Resolution of Issues Re to Rv Water Level Instrumentation in Bwrs ML20246D7731989-08-21021 August 1989 Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 2.2.1, Required Actions Based on Generic Implications of Salem ATWS Events. Equipment Classification Program for safety-related Components Acceptable ML20244D0311989-06-0707 June 1989 Safety Evaluation Accepting Util Second 10-yr Interval Inservice Insp Program Plan ML20205T4181988-10-14014 October 1988 Errata to Safety Evaluation Concluding Util Submittal Re Spent Fuel Pool Expansion ML20204F7271988-10-14014 October 1988 Safety Evaluation Supporting Proposed Expansion of Spent Fuel Pool at Facility ML20236N6461987-08-0707 August 1987 Safety Evaluation Re Permanent Elimination of Liquid Penetrant Exam of Feedwater Nozzles at Facility.Due to Lack of Reasonable Assurance That Ultrasonic Exam Can Totally Replace Penetrant Exam,Request Unacceptable ML20214T9891987-05-28028 May 1987 Safety Evaluation Re Util 870112 Proposed Plans to Inspect Two Overlay Repaired Core Spray safe-ends in Lieu of Replacement During Upcoming 1987 Refueling Outage.Plans Acceptable,Providing That Insp Results Satisfactory ML20207S7801987-03-12012 March 1987 Safety Evaluation Granting Relief from Tech Spec 4.7.A.3 on one-time Basis to Perform RHR Pump Wear Ring Replacement ML20214T4921986-11-24024 November 1986 Safety Evaluation Accepting Licensee 830511 & 860117 Responses to Generic Ltr 83-08 Re Mod of Vaccum Breakers on Mark I Containments ML20215M5871986-10-24024 October 1986 Preliminary Evaluation of Containment Study Transmitted w/860902 Ltr.Licensee Estimates Appear Optimistic Considering Uncertainties Inherent in Failure Rate Data ML20206F3651986-06-16016 June 1986 Safety Evaluation Re Proposed Repair of Core Spray safe- Ends,During Current Refueling Outage.Plant Can Be Safely Returned to Power Operation After Satisfactory Completion of Core Spray safe-end Repairs ML20206F0681986-06-13013 June 1986 Safety Evaluation Supporting 850514,0710,860327,0411 & 0513 Requests for Approval to Use Pvrc Damping Values (ASME Code Case N-411) for Piping Sys Reanalysis ML20202J4211986-03-31031 March 1986 Safety Evaluation Accepting Util Design Mods & Tech Spec Changes Re Degraded Grid Voltage Protection for Class 1E Sys.Lll Technical Evaluation Rept Encl ML20155B8351986-03-31031 March 1986 Safety Evaluation Supporting Revised Procedure OP-3140, Providing Technically Acceptable Actions During Degraded Grid Voltage Conditions W/O LOCA to Assure Protection of Class 1E Electrical Sys & Equipment ML20140H9881986-03-25025 March 1986 Safety Evaluation Re Util 851008 Request to Install Carpet Over Vinyl Asbestos Tiled Control Room Floor Covering. Installation of Carpet Will Not Decrease Level of Fire Safety in Control Room & Deviation Acceptable ML20138E4201985-12-0202 December 1985 Safety Evaluation Supporting Util 831107 & 840320 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability ML20136F1241985-11-18018 November 1985 Safety Evaluation Re IE Bulletin 80-11, Masonry Wall Design. Issues Re Arching Action Theory Resolved ML20137S7331985-09-27027 September 1985 Safety Evaluation Approving Use of Fuel Thermal Performance Code,Frosstey,For Analysis of LOCA Conditions at Low & Moderate Burnups ML20135C8921985-09-10010 September 1985 Safety Evaluation Supporting 840824 Commitment to Convert Air Containment Atmosphere Dilution Sys to Nitrogen Sys,In Response to Generic Ltr 84-09 ML20135C9121985-09-10010 September 1985 Safety Evaluation Supporting Conclusion That Diversification of Scram Discharge Vol Level Instrumentation Not Necessary & Tech Specs,As Modified in Amend 76,resolve Staff Concerns Re Need for Instrumentation Diversity ML20134K7351985-08-19019 August 1985 Safety Evaluation Accepting 831107 Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing ML20136G3611985-08-12012 August 1985 Safety Evaluation Accepting Seismic Design Criteria Utilized for Evaluation of Modified Recirculation Sys ML20132D8971985-07-22022 July 1985 Safety Evaluation Supporting Use of Pvrc Damping Values (ASME Code Case N-411) for Response Spectrum Seismic Piping Analyses ML20127D8991985-05-0606 May 1985 Safety Evaluation Re 840925 & 1002 Responses to Generic Ltr 83-28,Item 1.1 Concerning post-trip Review Program & Procedures.Program & Procedures Acceptable 1999-09-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8831999-10-21021 October 1999 Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 BVY-99-127, Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 BVY-99-112, Monthly Operating Rept for Aug 1999 for Vermont Yankee.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Vermont Yankee.With BVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999 Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831 BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Vermont Yankee. with ML20209J0081999-07-14014 July 1999 Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With ML20196G5071999-06-23023 June 1999 Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With BVY-99-068, Monthly Operating Rept for Apr 1999 for Vynp.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Vynp.With ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application ML20206D9301999-04-27027 April 1999 1999 Emergency Preparedness Exercise 990427 Exercise Manual (Plume Portion) ML20205S4211999-04-16016 April 1999 Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With ML20205P8241999-02-28028 February 1999 Rev 2 to Vermont Yankee Cycle 20 Colr ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20203A6951999-02-0404 February 1999 Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam) ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification ML20199K6991999-01-20020 January 1999 Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable ML20199L5951999-01-14014 January 1999 Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i) BVY-99-071, Corp 1998 Annual Rept. with1998-12-31031 December 1998 Corp 1998 Annual Rept. with BVY-99-001, Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station ML20198H5481998-12-23023 December 1998 Rev 2 to Vermont Operational QA Manual,Voqam ML20196H8641998-12-0101 December 1998 Cycle 19 Operating Rept BVY-98-163, Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With ML20195C4161998-11-0909 November 1998 SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds BVY-98-154, Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With ML20155B6471998-10-26026 October 1998 Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage ML20154N0891998-10-16016 October 1998 Rev 1 to Vermont Operational QA Program Manual (Voqam) ML20154B6951998-10-0101 October 1998 SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station BVY-98-149, Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With ML20239A1361998-09-0202 September 1998 SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program BVY-98-135, Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With ML20151U0361998-08-28028 August 1998 Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project ML20237E9221998-08-20020 August 1998 Vynp 1998 Form NIS-1 Owners Summary Rept for ISI, 961103-980603 BVY-98-122, Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station ML20205F6491998-07-31031 July 1998 Rev 1 to GE-NE-B13-01935-02, Jet Pump Assembly Welds Flaw Evaluation Handbook for Vermont Yankee ML20236G0011998-06-30030 June 1998 Individual Plant Exam External Events BVY-98-098, Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station ML20248C5081998-05-31031 May 1998 Rev 2 to 24A5416, Supplemental Reload Licensing Rept for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20 ML20248C4951998-05-31031 May 1998 Rev 1 to Vermont Yankee Nuclear Power Station Cycle 20 Colr BVY-98-081, Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station ML20247J8341998-05-31031 May 1998 Peak Suppression Pool Temp Analyses for Large Break LOCA Scenarios, for May 1998 ML20247G4001998-05-12012 May 1998 Interview Rept of Ej Massey ML20247E6351998-04-30030 April 1998 Rev 1 to GE-NE-B13-01935-LTR, Jet Pump Riser Welds Allowable Flaw Sizes Ltr Rept for Vermont Yankee 1999-09-30
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UNITED STATES g NUCLEAR REGULATORY COMMISSION
- WASHINGTON, D.C. seess 4001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING REACTOR VESSEL INTERNALS INSPECTION AND REPAIR ACTIVITIES DURING THE 1998 AND 1999 REFUELING OUTAGES VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 1
1.0 INTRODUCTION
By letter dated September 30,1997, Vermont Yankee Nuclear Power Corporatum (the licensee) submitted its inspection plans for the Vermont Yankee Nuclear Power Station (VY) spring 1998 and fall 1999 refueling outages for NRC staff review and approval. The licensee intends to use the recommendations of several Boiling Water Reactor Vessel and intemals Project (BWRVIP) guidelines in the performance of intemal component examinations and evaluationa 6Jring the upcoming refueling outages.
2.0 EVALUATION The licensee provided its evaluation of several reactor pressure vessel (RPV) intemal components. The NRC staff review of the licensee's submittal follows.
Core Shroud The licensee stated that an ultrasonic inspection of the VY circumferential welds was completed in the spring of 1995, and as a result of that inspection a full circumferential weld repair, consisting of four tie rods, was performed in the fall of 1996. In conjunction with the repair, ultrasonic and oddy current inspections of the repair design reliant welds was also performed during the fall 1996 outage. The design reliant welds consist of portions of eight vertical welds, six ring segment welds and portions of welds H8 and H9 at the jet pump baffle plate. The licensee reported that no cracking was found in any of these welds. Further, the licensee stated I that the 1996 vertical and ring segment weld inspections will meet the BWRVIP guidelines for reinspection of BWR core shrouds (BWRVIP-07) for a complete baseline inspection of repaired shrouds, as revised. The licensee stated that during its spring 1998 outage that it will perform the first cycle inspection of all four tie rods, which will consist of a visual examination. The staff finds the above to be acceptable.
Shroud Buoport 1
in the fall of 1996, the licensee performed ultrasonic and oddy current inspection of welds H8 and H9 and no cracking was found. The BWRVIP is drafting shroud eupport inspection and flaw i evaluation guidelines; however, the licensee states that the VY fall 1996 inspection meets the current BWRVIP draft guidelines for a baseline examination. The staff finds this acceptable for the upcoming outage, but notes that the licensee may need to revise its plans based on the staff's review of the BWRVIP report, when submitted.
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2-Core Sprav Piping The licensee stated that it performed ultrasonic inspection of 39 core spray piping circumferential
. welds and visual inspection of 5 circumferential welds that were not accessible for the ultrasonic inspection during its fall 1996 outage, which represented 100 percent of the accessible core spray piping welds, and that these inspections met the requirements of the BWRVIP Core Spray
- Intemals inspection and Fisw Evaluation Guidelines (BWRVIP-18) for a baseline examination.
Two non-pressure boundary mechanical welds, where the core spray piping penetrates the core shroud, were found to have indications of possible intergranular stress corrosion cracking ~
. (lGSCC). The flaw analysis evaluated several possible conditions of the core spray piping, '
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including the limiting case where all four mechanical collar welds were completely failed.
' The staff evaluated the licensee's analysis and authorized operation through the end of Cycle 19
. without performing weld repairs. Operation beyond Cycle 19 would depend on the satisfactory evaluation of the reinspection results or by implementing acceptable repairs during the next
- refueling outage. The licensee stated that it will role.spect the five wolds that were inspected visually in the fall 1996 outage during the spring 1998 outage, and will visually reinspect the two core spray piping welds that exhibited possible cracking. Further, the licensee stated its intention to fully replace the core spray piping system intemal to the reactor vessel (excluding the spargers) during its 1999 refueling outage, and , as such, does not plan to repair the cracked core spray pipe collar welds unless the reinspection warrants such a repair. The staff finds this to be acceptable Core Soray Spargers The licensee has been following the requirements of IE Bulletin 8013 for the inspection of core spray spargers. Beginning with the spring 1998 outage, the licensee intends to follow the guidance of the BWRVIP Core Spray Intemals inspection and Flaw Evaluation Guidelines (BWRVIP-18). The staff finds this position to be acceptable, but notes that the staff's review of the BWRVIP 18 report may necessitate modifications to the licensee's re-inspection schedule or may require other actions.
Too Guide The licensee stated that it had completed GE SIL No. 588 inspection recommendations in the fall 1996 refueling outage and will continue to perform examinations as recommended by GE SIL No.
554. They will perform visual inspections of top guide beams as they become accessible during the normal course of refueling operations. Further, the licensee intends to install top guide wedges during the fall 1999 refueling outage and will acquire the necessary dimensional information during the spring 1998 retuoling outage. Because the licensee intends to install top
- j. guide wedges in 1999, it does not plan to perform any supplemental inspections of the top guide alignment hardware in 1998, except as in preparation for the 1999 refueling outage.
. The BWRVIP Top Guide Inspection and Flaw Evaluation Guidelines (BWRVIP-26) were published in December of 1996 and would require for VY a VT-1 inspection of welds in two
- adjacent alignment assemblies every other cycle and a visual inspection every other cycle of rim weld locations made accessible during normal refueling activities. The licensee stated that the
' welds in question are virtually inaccessible for visual inspection, and that a "best effort" visual examination (similar to a VT-3 examination) of two of the alignment assemblies was performed
3-in 1996. Further, the licensee stated that ultrasonic inspection of these welds was investigated and, while accessibility to some of the welds is improved, the majortty would still not be accessible, even from allemative surfaces. Additionally, there are no vendor tools that currently exist or are in development to provide better access for either ultrasonic or visual inspection.
Finally, the BWRVIP inspection Committee has not yet provided guidance on the examination of the above top guide components. Based on the above, the staff concludes that the proposed course of action is acceptable.
Core Plate The licensee stated its intentions to install core plate wedges during the fall 1999 refueling outage which would preclude the need for inspection of the core plate rim hold-down bolts, as is required by the BWRVIP Core Plate inspecticn and Flaw Evaluation Guidelines (BWRVIP-25),
' which is still under staff review. Since the licensee intends to install core plate wedges in 1999, it does not plan to perform any inspection on the core plate in 1998, except as in preparation for
. the 1999 refueling outage. GE SIL No. 588 inspection recommenda'Jons were completed during the fall 1996 refueling outage. Based on the above, the staff concludes that the proposed course of action is acceptable.
Jet Pump Assemblies The licensee stated its intention to perform inspections of the jet pump assemblies during the 1998 or 1999 outage in accordance with the BWRVIP Jet Pump Assembly inspection and Evaluation Guidelines (BWRVIP-41), which is presently under staff review. The current BWRVIP draft guidelines require a 50% sample of the high priority welds (essentially all of the circumferential welds in the riser, mixer, diffuser and adaptor pieces) at the nex1 refueling outage.
There are approximately 190 of these welds at VY. In accordance with recommendations in NUREG/CR-3052, VY also intends to perform ultrasonic inspection of the jet pump hold-down beams during the 1998 refueling outage.
Since several plants have detected cra:: king in jet pump riser circumferential welds, inspection of these components should be of highr priority to the licensee, and the staff requests that a best-effort inspection be performed during the 1998 outage, with followup during the 1999 outage.
Standbv Linuld Control Svstem The licensee stated its intention to follow the BWRVIP Standby Liquid Control System inspection and Flaw Evaluation Guidelines (BWRVIP-27) and inspect the nozzle-to-safe end weld extemal to the vessel _if a technique is developed in time for the 1998 refueling outage.
The staff notes that at VY the standby liquid control system safe end is low carbon (0.019%)
stainless steel material, and thus not considered to be susceptible to IGSCC. However, the staff encourages that this inspection be peformed.
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3.0 CONCLUSION
The NRC staff concludes that the proposed actions, as described above, are acceptable. Based on the above, the NRC staff has concluded that there is reasonable assurance that plant
. operation in this manner poses no undue risk te the health and safety of the public.
The NRC staff Is presently reviewing several BWRVIP documents, and, while the NRC staff has not identified any major deficiencies in the BWRVIP's technical assessments, neither has the NRC staff made a determination as to their overall acceptability. Therefore, if concoms are found during the review of the several BWRVIP reports and the licensee follows the BWRVIP guidance, the NRC staff may request that the licensee also address these concems on a plant-specific basis.
Principal Contributor: C. E. Carpenter Date: Ma rch 25, 1998 d
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