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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20217Q6701998-05-0606 May 1998 SER Approving Proposed Postponement of Beginning Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) at Grand Gulf for Circumferential Shell Welds for Two Operating Cycles ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20217P0381998-04-0606 April 1998 Safety Evaluation Supporting Amend 135 to License NPF-29 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20199F3431997-11-18018 November 1997 SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1 ML20216E9921997-09-0404 September 1997 Safety Evaluation Accepting 970623 Request for Relief Re Authorization for Use of ASME Code Case N-416-1 & N-532,ISI Program for Listed Plants ML20134C5671997-01-30030 January 1997 SER Denying Request for Exemption from 10CFR50.55a Entergy Operating,Inc Et Al,Grand Gulf Nuclear Station,Unit 1 ML20149M4221996-12-12012 December 1996 Safety Evaluation Supporting Update Insvc Insp Programs to 1992 & Portions of 1993 ASME Boiler & Pressure Vessel Code, Sect XI for Licenses DPR-51,NPF-6,NPF-38,NPF-29 & NPF-47. Technical Ltr Rept Encl ML20138B5681996-12-11011 December 1996 Safety Evaluation Re Emergency Plan Change 28.001-95 to Entergy Operations,Inc,Grand Gulf Nuclear Station ML20134K5321996-11-18018 November 1996 Safety Evaluation Supporting Request for Relief Re 10CFR50.55a Inservice Testing of Main Steam Safety/Relief Valves for License NPF-29 ML20129D0441996-10-22022 October 1996 Safety Evaluation Supporting Request for Relief I-00014 ML20129B8751996-10-18018 October 1996 Safety Evaluation Accepting First 10-year Interval ISI Program Plan Addl Request for Relief ML20128H2491996-10-0707 October 1996 Safety Evaluation Authorizing Licensee Proposed Alternative to Use ASME Code Case N-508-1 for Rotation of Serviced Snubbers & Pressure Relief Valves for Sole Purpose of Testing in Lieu of ASME Requirements ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML20128N1381993-02-17017 February 1993 Safety Evaluation Accepting Proposal to Raise Design Ground Water Level from 109 Ft Above Msl to 114.5 Ft Above Msl ML20058B4411990-10-25025 October 1990 Safety Evaluation Granting 900709 Request for Relief from Requirements for Leakage Testing of RCS in ASME Code,Section XI ML20062A1941990-10-16016 October 1990 Safety Evaluation Granting Relief Request from Inservice Insp Requirements ML20059N4971990-10-0101 October 1990 Safety Evaluation Accepting Util Response to Generic Ltr 88-01,w/listed Exceptions ML20058N3941990-08-0606 August 1990 Generic SER Re Mark III Containment Hydrogen Control, Concluding That HGN-112-NP, Generic Hydrogen Control Info for BWR-6 Mark III Containments Provides Acceptable Basis for Technical Resolution of Degraded Core Hydrogen Issue ML20055G5271990-07-18018 July 1990 Safety Evaluation Re Facility Procedures Generation Package. Util Needs to Revise Package to Address Programmatic Improvements Identified ML20055G0341990-07-16016 July 1990 Safety Evaluation Re Boraflex Gaps in Spent Fuel Racks. Storage Racks Can Safely Accomodate Max Reactivity of Unit 1 Cycle 1 Through Cycle 4 Fuel.Storage Rack Surveillance Program Acceptable for long-term Storage of Spent Fuel ML20055F9081990-07-16016 July 1990 Safety Evaluation Accepting Criticality Analysis for Cycle 5 Fuel in Spent Fuel Storage Racks ML20246D8021989-08-21021 August 1989 Safety Evaluation Granting 880524 Requests for Relief from Certain Requirements of ASME Code,Section XI ML20246B6311989-08-17017 August 1989 Safety Evaluation Supporting Amend 25 to License NPF-62 ML20247G7041989-07-21021 July 1989 SER Accepting Licensee Commitment to Install ex-core Neutron Flux Monitoring Instrumentation Meeting Requirements of Reg Guide 1.97,Rev 2,prior to Restart Following Fourth Refueling Outage ML20245A8251989-04-17017 April 1989 SER Re Proposed Changes to Administrative Controls Section of Tech Specs Concerning Min Shift Crew Composition,Unit Staff Qualifications,Training,Plant Safety Review Committee & Safety Review Committee Composition.Changes Unacceptable ML20244D5291989-04-14014 April 1989 Safety Evaluation Supporting Util Actions in Response to Generic Ltr 83-28,Position 4.5.2, Testing of Reactor Trip Sys. Justification for Not Testing Reactor Mode Switch or Backup Scram Valves Provided ML20248J9001989-04-0505 April 1989 Safety Evaluation Accepting Licensee Statements Confirming That Vendor Interface Program Exists W/Nsss Vendor for Components Required for Performance of Reactor Trip Function ML20151P0291988-08-0505 August 1988 Safety Evaluation Supporting Generic Ltr 83-28,Position 4.5.1 Re on-line Testing of Reactor Trip Sys ML20234D9021987-12-30030 December 1987 Safety Evaluation Supporting 870612,0814,1026 & 1119 Relief Requests from First 10-yr Interval Inservice Insp Program Requirements of Section XI of ASME Code ML20149E7091987-12-30030 December 1987 Safety Evaluation Supporting Amend 41 to License NPF-29 ML20234C7671987-12-23023 December 1987 Safety Evaluation Granting 870612,0814,1026 & 1119 Requests for Relief from Certain Section XI ASME Code Requirements Re First 10-yr Interval Inservice Insp Program ML20236B1021987-10-15015 October 1987 Safety Evaluation of 870630 Submittal Supplemented on 870821 & 0911 Re Deferral of Certain Insps of Tdi Div II Emergency Diesel Generators.Deferral of Certain Design Review & Quality Revalidation Baseline Insps Approved ML20235V1701987-10-0707 October 1987 Safety Evaluation Re 861022 Rev 2 to Process Control Program (PCP) for Processing & Packaging of Wet Radwastes.Pcp Acceptable ML20234A9471987-09-0404 September 1987 Safety Evaluation Re Util 870702 Submittal Re Containment Isolation for Various Instrument Lines.Util Proposed Alternate Basis to Meet GDC 55 to 10CFR50 App a Acceptable ML20237H1711987-08-21021 August 1987 Safety Evaluation Supporting Util 851014,870403 & 870622 Submittals Providing Info Re ATWS-related Design Features, Alternate Rod Injection,Standby Liquid Control Sys & Recirculation Pump Trip ML20236M3841987-07-31031 July 1987 Safety Evaluation on Generic Ltr 83-28,Items 3.1.1,3.1.2, 3.2.1 & 3.2.2 Re post-maint Testing.Licensee Programmatic Controls & Procedures for post-maint Testing of Components in Reactor Trip & safety-related Sys Acceptable ML20215J1351987-05-0404 May 1987 Safety Evaluation Re Spill of Sulphuric Acid at Plant on 860322.Licensee Monitoring & Recovery Sys Adequate to Contain & Eliminate Existing Acid Plume.No Addl Measures Recommended ML20210C3391987-04-30030 April 1987 Safety Evaluation Accepting Licensee 870129 Proposed Solution to Concern Re Control of Activities within Exclusion Areas ML20204J1451987-03-23023 March 1987 SER Supporting Licensee Responses to Humphrey Concerns on Safety of Mark III Containment Design ML20207R1051987-03-0505 March 1987 Safety Evaluation Supporting Util 861125 Rept on Conformance to Reg Guide 1.133,Rev 1, Loose-Part Detection Program for ...Sys of Light Water Cooled Reactors. License Condition 2.C(14) Adequately Addressed ML20212M3861987-03-0404 March 1987 Safety Evaluation Accepting Util 861223 Response to IE Bulletin 79-26, Boron Loss from BWR Control Blades, Per License Condition 2.C.(12) ML20207N2761987-01-12012 January 1987 SER Supporting License Condition 2.C.(17) Which Replaces Check Valve Disc in Train B Feedwater Line Into Which Cold Water from Condensate Storage Tank Injected by RCIC ML20212G3421987-01-12012 January 1987 Safety Evaluation Accepting Util 850228 & 860214 Submittals on Conformance to Reg Guide 1.97,Rev 2 ML20211P3901986-12-12012 December 1986 SER Supporting Util 860825 Request for Rev to Relief Request I-00007 Seeking Relief from Surface Exam for Welds within Flued Heads & Guard Pipes ML20214W8161986-12-0808 December 1986 Safety Evaluation Granting Util 861015 Request for Release from Commitment to Compare Performance of on-line Instrumentation Vs Grab Sampling Techniques 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With ML20211A6921999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20209J1961999-07-12012 July 1999 Special Rept 99-001:on 990528,smoke Detectors Failed to Alarm During Performance of Routine Channel Functional Testing.Applicable TRM Interim Compensatory Measure of Establishing Roving Hourly Fire Patrol Was Implemented ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20209G0691999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20196A1161999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Grand Gulf Nuclear Station.With ML20206Q4831999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Grand Gulf Nuclear Station Unit 1.With ML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205P8771999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207K5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20207A8301998-12-31031 December 1998 1998 Annual Operating Rept for Ggns,Unit 1 ML20206R9501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20206D7721998-12-31031 December 1998 South Mississippi Electric Power Association 1998 Annual Rept ML20198E2481998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20195F4121998-11-13013 November 1998 Rev 16 to GGNS-TOP-1A, Operational QA Manual (Oqam) ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20195C2791998-11-0505 November 1998 BWR Feedwater Nozzle Inservice Insp Summary Rept for GGNS, NUREG-0619-00006 ML20195F4801998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K2391998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Grand Gulf Nuclear Station Unit 1.With ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20153B2161998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20237B6661998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Grand Gulf Nuclear Station,Unit 1 ML20236R0231998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Grand Gulf Nuclear Station,Unit 1 ML20155J0811998-05-31031 May 1998 10CFR50.59 SE for Period Jan 1997 - May 1998 ML20249B1251998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Grand Gulf Nuclear Station,Unit 1 ML20248B6261998-05-11011 May 1998 Rev 6 to Grand Gulf Nuclear Station COLR Safety-Related ML20217Q6701998-05-0606 May 1998 SER Approving Proposed Postponement of Beginning Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) at Grand Gulf for Circumferential Shell Welds for Two Operating Cycles ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20247F3591998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Grand Gulf Nuclear Plant,Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20217P0381998-04-0606 April 1998 Safety Evaluation Supporting Amend 135 to License NPF-29 ML20217A0291998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Grand Gulf Nuclear Sation,Unit 1 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station ML20216J2021998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Grand Gulf Nuclear Station,Unit 1 ML20203A2891998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Grand Gulf Nuclear Station ML20247B4111997-12-31031 December 1997 1997 Annual Financial Rept for South Mississippi Electric Power Association ML20203H9741997-12-31031 December 1997 1997 Annual Operating Rept, for Ggns,Unit 1 ML20198P1121997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Grand Gulf Nuclear Station,Unit 1 ML20203B5581997-12-0404 December 1997 Special Rept 97-003:on 971111,valid Failure of Div 2 EDG Occurred,Due to Jacket Water Leak.Failure Reported,Per Plant Technical Requirements Manual Section 7.7.2.2 ML20203K4031997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Grand Gulf Nuclear Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20199F3431997-11-18018 November 1997 SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1 1999-09-09
[Table view] |
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n UNITED STATES L s* .i NUCLEAR REGULATORY COMMISSION D Y, ,
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIQN RELATED TO GROUND WATER LEVEL CONTROL AND MONITORING ENTERGY OPERATIONS. INC.
MAND _ GULF NUCLEAR STATION DOCKET NO. 50-416
1.0 INTRODUCTION
The licensee, Entergy Operations Inc. (E01) (formerly Mississippi Power &
Light Co.), submitted a detailed report in April 1992 describing actions t'aken to resolve the ground water issue at Grand Gulf Nuclear Station (GGNS) pending since 1985 (Ref. 1). In its final effort to resolve this issue, E01 proposed two actions, namely,1) raise the Design Ground Water Level-(DGWL) from Elevation (El) 109 feet (ft) above mean sea level (msl) to El 114.5 ft above msl, and 2) discontinue ground water level (GWL) monitoring. The staff reviewed E01's report and found its proposals acceptable as discussed below.
The power block structures at GGNS are founded on the Catahoula Formation which is comprised of dense claystone. The material overlying the Catahoula Formation consists of terrace deposits, loess, and alluvium. The power block structures and the Stand-by Service Water (SSW) basins for Grand Gulf Units 1 and 2 were constructeo within an open excavation that extended from yard grade at El 132.5 ft msl to the Catahoula Formation at about- El 37 ft msl (Ref.1).
This excavation was perforned inside a tieback wall; as the strcctures were completed, the area between the tieback wall and the building walls was backfilled with a granular material and capped with a 2-ft thick clay surface seal to minimize rainfall infiltration and recharge of ground water.
Historically, GWLs in the power block area have been at elevations higner than the regional GWL, which occurs generally at an elevation of about 75 ft, north and se'ith of the plant area. The average GWl. at the plant is about 100 ft, which eflects a mounded condition coinciding with a rise in the top of the underlying Catahoula Formation.
Seven monitoring wells (MW-1 through MW-7) were installed around the power block in 1976 to replace the 11 construction observation wells destroyed during the start of construction in 1975. These wells are 6-inch diameter PVC pipe installed within the ba:kfill. Seepage of ground water into the excavation was initially controlled by pumping from sumps and later by a dewatering well system that was installed in 1979 and 1980. The construction dewatering system consisted of eight 10-inch diameter wells (DW-1 through DW-8). Later, five monitoring wells (MW-8 through MW-12) were installed to
. monitor water levels in the circulating water pipe trench (CWPT) backfill and in the terrace deposits east of the power block, and fifteen monitoring wells (MW-13 through HW-26) were installed in the terrace deposits in the vicinity 9302230080 930217 &.
DR ADOCK 0500
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of the cooling tower and in the north site area to better define ground water flow patterns across the site and recharge sources.
Water levels in well DW-8, which was installed it. July 1980, have typically +
been higher than those recorded in other dewatering and monitoring wells in the power block area. The water level in well DW-8 exceeded the DGWL of-109.0 ft by up to 1.2 ft during January to June 1983. In December 1983, GGNS conducted the first of several " Ground Water Level Studies" to investigate the causes of exceedance of DGWL in DW-8, and reported the results of this study to NRC in February 1985. This report provided information regarding the effect of the exceedance on safety-related structures and equipment, precipitation data, models to calculate GWL and the dewatering systems for Units 1 and 2. The NRC staff reviewed the licensee's sebmi'ctal and issued a detailed safety evaluation on this issue, concluding that the reported exceedance of the DGWL did not compromise the integrity of the safety-related facilities (Ref. 2). However, this issue was considered an open item because the construction of Unit 2 including the backfilling and the clay seal was not completed. Considering the licensee's commitment to retain dewatering capability for Units 1 and 2 until completion of Unit 2 construction, and the low probability of occurrence of rainfall necessary to exceed a CWL of 109 ft msl, the staff concluded that final projection of the maximum post-construction ground water level and resolution of exceedance of the design basis GWL could be delayed for up to 5 years, but no later than December 1990.
If a final resolution of this issue was delayed beyond 1990, the licensee was required to provide, at that time, a status report and schedule for submittal of a final report (Ref. 2).
Since this issue was not resolved by December 1990, the licensee submitted several status rerorts. The first status report in December 1990 described five additional events of exceedance of OGWL due to malfunction or stopping of the dewatering pumps (Ref. 3). The licensee conducted two more " Ground Water Level Studies" in 1990 and 1991, as it did in 1983. Using the data from these studies, the licensee prepared a detailed report and proposed a resolution of the ground water level issue in April 1992 (Ref.1). The staff reviewed this report and requested additional information (Ref. 4), which the licensee has provided (Ref. 5). The staff's evaluation of the licensee's proposed resolution of high ground water level issue is given below.
2.0 EVALUATION In its detailed April 1992 report, the licensee summarized the results of several hydrological studies and structural and geotechnical calculations it has performed since 1983 (Refs. I and 5). The prir.cipal objectives of these studies were to: (1) ascertain the causes of exceedence of_DGWL; (2) determine the maximum possible GWL at the site and then propose a new DGWL; (3) evaluate the effects of raising the DGWL on the safety of structur6s and equipment; and (4) finally determine if GWL monitoring can be terminated.
The first of the above mentioned studies, performed in 1983, included structural calculations by its consultant, Bechtel Power Corpo ation, for the
c.
Unit I structures. These calculations indicated that the Cantrol Building and f the SSW basins are safe for a GWL elevation of 114.5 ft and the remaining safety-related structures are safe for a GWL elevation of 117.0 ft. The licensee also investigated the effect of raising the DGW'. on the in-structure response spectra by considering the changes in the dynamic soil properties'due to the raised DGWL. E01 found that the slight variations in soil properties had a minimal effect on structural response and that it.would be adequately enveloped by the +/- 15% broadening of the dcsign in-structure response spectra (Ref. 5).
The licensee conducted two more studies - one in 1990 and another in 1991.
The results of the study conducted in 1990 indicated that the sources of ground water within the power block area are leakage from the cooling tower and infiltration from precipitation. The 1991 study results confirmed the 1990 study findings. These studies were used to develop the post-construction GWL map and to determine the maximum GWL expected to occur at the site without the influence of the leakage from the cooling tower.
The post-construction GWL contour map shows the estimated average GWLs considered likely to occur at GGNS during the life of the plant. The map is based on GWLs that have occurred since the achievement of final site configuration, the elimination of cooling tower leakage (which had previously raised the plant GWL), and no further pumping.from the dewatering wells. E01 has determineJ the maximum expected post-coristruction GWL within the power block area to be 113 ft msl. E01 has reported that the leakage noticed at the cooling tower has been fixed (Ref. 5). In response to a staff query on this subject, E01 has stated that a major leak that occurred at a damaged expansion jo;nt in the warm-water inlet tunnel ender the ccoling tower basin had been fixed by installing a different type of seal (Refs.1, 4, & 5). Several minor expansion / contraction cracks in the tunnel walls were also repaired to prevent-degradation of rebars in the tunnel walls. Nonnheless, E01 has committed to perform a visual inspection of the cooling tower during each refueling outage to verify that no potential leakage paths exist (Ref. 5).
Based on the findings of the above studies, E01 has proposed to raise the DGWL from 109 f t to 114.5 ft for all structures within the power block. E01 determined the new DGWL by adding the highest recorded level (El 110.2) with minimum influence from the plant recharge source to the ...ghest GWL change (3 ft) from a period of heavy precipitation (Ref. 5). The staff accepts this proposal to raise DGWL for the following reasons:
- 1. The structural calculations by Bechtel Power Corporation indicates that all the safety-related structures are safe for a GWL of 114.5 ft.
- 2. In response to a staff question (Appendix I to Reference 1), E01 has stated that adequate factors of safety against liquef action within the Category I backfill exist for water levels up to El 124 ft, based or. its detailed engineering assessment of the seismic structural calculations.
y, L.
l o lk E01's second proposal deals with the discontinuance of GWL monitoring at GGNS.
As stated in Section 2.5.4.6 of the Updated Final Safety Analysis Report (UFSAR), the construction system was originally installed to remove seepage of ground water into the excavation and inflow of precipitation during construction. Since the Unit 2 construction has been terminated and the required backfill completed, repairs to the cooling tower completed, and the expected maximum GWL determined, the licensee sees no need to continue monitoring the plant GWL (Ref. 1). However, during a teleconference with E01's staff on December 23, 1992, the NRC staff was informed that the licensee will continue to maintain the ground water monitoring wells, and take.GWL measurements after heavy rainfall and also at intervals determined by its Civil Engineering personnel. E01's staff also stated that it will report to the NRC staff if the GWL exceeds the increased DGWL of 114.5 ft. However, the licensee proposes to discontinue measuring the GWLs monthly, as has been done so far in connection with the Environmental Report it submits to NRC. In view of the above commitments by E01, the staff accepts the licensee's proposal to discontinue the current GWL monitoring program.
3.0 CONCLUSION
Based on a review of the licensee's April 30, 1992,-report and its September 25, 1992 response to the staff's queries, the staff concludes that 3
the licensee has taken necessary steps to resolve the outstanding ground water issues at GGNS following the staff's detailed safety evaluation on this subject issued in August 1985 (Ref. 2). The staff accepts the licensee's
- proposal to raise the DGWL from 109 ft msl to 114.5 ft msl, as the structural calculations by its consultant, Bechtel Power Corporation, have shown that this action does not compromise the structural stability of the safety-related facilities due to the increased hydrostatic loading.
The staff accepts E01's proposal to discontinue the current GWL monitoring, subject to the following commitments made by E01 in its Septe:rber 1992 response (Ref. 5) and again during a teleconference on December 23, 1992:
- 1) continue to monitor the GWLs by measuring the water levels in a representative sample of the wells in the power block area at intervals determined by its engineering staff (and after periods of heavy rainfall), and report to NRC if the GWL exceeds revised DGWL, and 2) carry out a visual inspection of the cooling tower during each refueling outage to veri,fy that no potential leakage paths exist which would cause the GWL to rise above tne new DGWL.
4.0 RE FEREN,_(.[1
- 1. Letter from W. T. Cottle, EDI (formerly Mississippi Power and Light Co.),
to USNRC, dated April 30, 1992.
Subject:
Grand Gulf Nuclear Station Unit 1 - Resolution of High Ground Water Levels.
- 2. Letter from T. M. Novak, NRL, to J. B. Richard, E01, dated August 19, 1985.
Subject:
Grand Gulf Nuclear Station, Units 1 and 2 - High Ground Water Level.
1 l
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I. ..,'
l- .
- 3. Letter from W. T. Cottle, E01, to USNRC, dated December 21, 1990.
Subject:
Grand Gulf Nuclear Station Unit 1 - Ground Water Monitoring Program.
- 4. Letter from Paul W. O' Connor, USNRC, dated July 17, 1992.
Subject:
Grand Gulf Nuclear Station, Request for Additional Information
- 5. Letter from W. T. Cottle, E01, to USNRC, dated September 25, 1992.
Subject:
Grand Gulf Nuclear Station Unit 1 - Response to Request for Additional Information related to Ground Water Level Control and Monitoring.
Principal Contributor: R. Pichumani Date:
q
l
- ..> Mr. William T.- Cottle _ A copy of the staff's detailed safety evaluation is enclosed. This completes the staff's action on this issue.
Sincerely, Original signed by H. Rood for Paul W. O'Conncr, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation Enclosure.
Safety Evaluation cc w/ enclosure:
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^ Docket File NRC & Local PDRs PD4-1 Reading P. Noonan M. Virgilio J. Roe G. Hubbard PD4-1 Plant File P. O'Connor ACRS(10) OGC (15B18) L. Reyes, RII.
R. Pichumant 0FC LA:PD4 hA PM:PD4-1 M D:PD41 to ga r3- e-NAME PNoon, a n, / P0'Connor:pk GHubbard DATE l? / / / /93 8 /4 /93 'L/k7/93 i-0FFICIAL RECORD COPY Document Name: GG79323.ltr
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