|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20249B6281998-06-12012 June 1998 Safety Evaluation Accepting 980303 Request to Review & Approve Proposed Change to Plant,Units 1 & 2 TS Re Relocation of Meteorological Tower ML20248B0441998-05-27027 May 1998 Safety Evaluation Authorizing Proposed Alternative Use of Current TS Section 3/4.7.8 Requirements for Snubber Visual Exam & Functional Testing,Based on Finding That Proposed Alternative Proposes Acceptable Level of Quality & Safety ML20197A6551998-03-0202 March 1998 Safety Evaluation Supporting Licensee Proposed Action to Set Gwl Alarm at Higher Elevation than Current Level of El 731 Feet ML20203B1071998-02-0404 February 1998 Safety Evaluation Approving Proposed Alternative to Reactor Vessel Augmented Exam Requirement of Reactor Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A)(5) ML20199F3361998-01-28028 January 1998 Safety Evaluation Supporting 951227 Request for NRC Approval of Proposed EALs to McGuire Nuclear Station,Units 1 & 2 ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20211E6871997-09-22022 September 1997 SER Accepting DPC Responses to GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20148S2231997-07-0202 July 1997 Safety Evaluation Accepting Supplemental Test Program for Relief Request 1.4.2 for Units 1 & 2 ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20134P2421997-02-20020 February 1997 Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications ML20134G5551996-11-0707 November 1996 Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel ML20059G8601993-10-29029 October 1993 SE Granting 921130 Request for Relief from Requirements of 1986 Edition of ASME Boiler & Pressure Vessel Code,Section XI Re Inservice Insp of safety-related Snubbers During Second 10-yr Interval ML20057F4121993-10-12012 October 1993 Safety Evaluation Re Inservice Testing Program Requests for Relief.Alternatives Authorized Per 10CFR50.55a(a)(3) or Relief Granted Per 10CFR50.55a(f)(6)(i) ML20057A0361993-08-26026 August 1993 Safety Evaluation Supporting Amends 138 & 120 to Licenses NPF-9 & NPF-17,respectively ML20056H3191993-08-24024 August 1993 SER Accepting Proposed TS Changes Re RWST & Cla Boron Concentrations ML20126H3171992-12-28028 December 1992 Safety Evaluation Granting Extension of First 10-yr ISI Interval to Coincide W/Start of end-of-cycle 8 Refueling Outage ML20058N7961990-08-0909 August 1990 Safety Evaluation Approving Relief Request 89-01 Re ASME Code Test Requirements for Nuclear Svc Water Sys ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20247H7611989-07-18018 July 1989 Safety Evaluation Supporting Amends 100 & 82 to Licenses NPF-9 & NPF-17,respectively ML20246C4621989-06-29029 June 1989 Safety Evaluation Granting Request for Relief from Hydrostatic Testing Requirements of Section XI of ASME Code ML20247C0171989-05-18018 May 1989 Safety Evaluation Supporting Util Actions to Recover from 890307-08 Unit 1 Steam Generator Tube Rupture Event ML20235M7781989-02-23023 February 1989 Safety Evaluation Supporting Util 890505 Relief Request 88-04 Re Addition of Insp Port on Containment Spray HX 1A ML20154H2171988-05-18018 May 1988 Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program ML20236M9631987-11-0606 November 1987 Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue ML20236A2901987-10-14014 October 1987 SER Supporting Util Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20236H5291987-07-31031 July 1987 Safety Evaluation Granting Util 870407 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys ML20214M3361987-05-22022 May 1987 Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing ML20209B1511987-01-28028 January 1987 SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing ML20207E7551986-12-30030 December 1986 SER Supporting Removal of RCS Thermal Sleeves ML20212D7271986-12-29029 December 1986 SER Re Util 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs for Reactor Trip Sys Components. Response Acceptable.Item 2.1 Closed ML20212D7411986-12-29029 December 1986 Safety Evaluation Re Util 850827 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys.Relief Justified ML20206M5621986-08-13013 August 1986 SER Accepting 840808 & 850621 Responses to IE Info Notice 84-90, Main Steam Line Break Effect on Environ Qualification of Equipment. Higher Temp Will Not Preclude Ability to Shut Down Reactor in Safe Shutdown Condition ML20215A9671986-05-22022 May 1986 SER Re Util 851207 Proposed Changes to Tech Specs Pertaining to Reactor Trip Sys Instrumentation & Surveillance,Per Generic Ltr 85-09.Proposed Tech Specs Should Be Submitted for Review,Per Generic Ltr.Salp Input Also Encl ML20137Y1761986-02-28028 February 1986 SER Accepting SPDS for Interim Implementation Until Listed Open Items Resolved ML20137T8871986-02-0606 February 1986 Safety Evaluation Supporting SPDS as Interim Implementation Until Open Issues Resolved.Issues Include Hot Leg Temp,Rhr Flow Rate,Stack Monitor,Steam Generator Radiation & Containment Isolation ML20138R5841985-10-31031 October 1985 Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.1.3,3.2.1,3.2.2,3.2.3,4.1 & 4.5.1 ML20134B8221985-08-0606 August 1985 Sser Supporting Dcrdr ML20128G1111985-06-21021 June 1985 SER of Util Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review (Data & Info Capability).Response to Item 1.2 Complete & Acceptable ML20129D5521985-05-30030 May 1985 SER Accepting Licensee Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review Program Description & Procedure ML20126J3601981-04-30030 April 1981 Safety Evaluation Re Emergency Preparedness Evaluation Rept 1999-09-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20199E0301998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20198D7561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199E0491998-11-30030 November 1998 Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20196G0581998-11-0606 November 1998 Rev 17 to COLR Cycle 13 for McGuire Unit 1 ML20196G0761998-11-0606 November 1998 Rev 15 to COLR Cycle 12 for McGuire Unit 2 ML20198D7771998-10-31031 October 1998 Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E5961998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154L6251998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E6021998-09-30030 September 1998 Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154B4131998-09-22022 September 1998 Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20154L6321998-08-31031 August 1998 Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1 ML20153B3741998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20237B2381998-07-31031 July 1998 Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2 ML20153B3931998-07-31031 July 1998 Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days 1999-09-30
[Table view] |
Text
. . . . -- ._ - _ . - . _ - - . - - - - .
p esa y p k UNITED STATES
.j#
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30HM001
\ * . . . + ,/
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GROUNDWATER ALARM IN WELL Mk GWA 2 DUKE ENERGY CORPORATION MCGUIRE NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-389 AND 50 370 BACKGROUND This safety evaluation addresses Special Report (SR) No. 96-04 dated November 14,1996, and subsequent revisions, which were submitted by Duke Energy Corporation (the licensee), as requirsd by Selected Licensee Commitment (SLC) No.16.9 8, Groundwater Level Monitoring System? The plant grade levelis at elevation (EI) 760 feet above mean sea level (mst). The maximum groundwater level (GWL) is considered to be at El 760 feet mal, based on a full level of 760 feet at Lake Norman, which borders the north side of the plant site (Ref.1).
Since the elevations of several Category I structures, including the Reactor Buildings (RBs) and the Auxiliary Building (AB), are below the natural GWL, a seismic Category I permanent dewatering underdrain system (UDS) was installed during initial construction to lower the water table. A detailed description of the UDS is given in Section 2.4.13 of the Final Safety Analysis Report (FSAR), and in the staffs Safety Evaluation Reports (SERs), dated March 1978 (Ref. 2),
and March 2,1989 (Ref. 3). The UDS incorporates a grid of interconnected flow channels on approximately 20 foot centers, located at the top of rock or fill concrete below the foundation slabs (Refs.1,2, and 3). These flow channels were formed by embedding woeden drain boxes' in concrete as shown in FSAR Figure 2-63. All channels drain by gravity to three sumps in the AB. In addition to these flow channcis, there are exterior wall drains consisting of zoned sand and stone filter and an 8-inch perforated metal pipe.
At the licensing stage, the staff concluded that the dewatering system provided an acceptable method of controlling the ground water levels at the site. However, the staff requested and the license committed to provide a comprehensive monitoring network (11 monitors) to assure early detection of UDS malfunction. The monitors in the immediate vicinity of the exterior wall drains were desigteed to sound an alarm in the control room when the groundwater level reached the level specified in the Technical Specifications (TS).
3 During a recent teleconference, the licensee stated that the wooden drain boxes were not load bearing structural members, and that they were protected from collapse by placing the concrete in thin layers on top of the boxes and on their sides so that the load from subsequent pours would be mostly borne by the concrete below.
l 9903090341 990302 PDR ADOCK 05000369 P PDR
2-In October 1984, the licensee applied for changes in TS Section 3/4.7.13 " Groundwater Level,"
and submitted a revised application in January 1988 seeking significant modification of the UDS I monitoring program. The modification involved: (1) the deletion of 6 of the 11 monitoring wells from the TS, and (2) the requirement for 3 of the 5 remaining wells (shown in FSAR Figure 2 62) to exceed the Hi Hi alarm level (El 731 feet ms!), before the initiation of the plant shutdown. The licensee requested this TS change based on the results of its detailed etructural analyses of the RBs and the AB (Ref. 3).
The NRC staff audited the calculations in April 1988 and found them acceptable. Therefore, the staff agreed that it was not necessary to continue monitoring the groundwater monitors next to the RBs or the interior groundwater monitors inside the Diesel Genera ^or Buildings (DGBs).
The five remaining monitors (one exterior monitor on the west exterior wall of the AB, one exterior monitor on the east exterior wall of the AB, and three interior monitors along the north exterior wall of the AB) were deemed sufficient to monitor all sides of the AB that are not bordered by the Turbine Building and the RBs. However, the licensee committed to maintain all 11 monitors in operable condition, even though the TS action statements would be based on fiv6 monitors, and included the six non TS monitors in SLC 16.9-8 (Ref.1, page 2-49). At the time of approving the above changes in the TS, the staff had determined that localized groundwater rise on a segment e"he building perimeter was no longer a significant safety concem, and that it was an indication of a partial system degradation that called for maintenance or corrective action in accordance with the licensee's administrative procedures.
On October 6,1996, the licensee received a groundwater alarm for Well Mk. GWA 2, which is located 66 inches away from the Unit 2 RB, and entered this incident in the TS Action item List for tracking, even though it was not a TS monitor. The alarm cleared within 7 days, but returned on October 11,1996, and cleared after 22 days. Since the alarm stayed on for more than 7 days, the licensee submitted to NRC, SR No. 96-04, in accordance with SLC 16.9.8 (Ref. 4), and subsequently submitted revisions 1 and 2 to the SR 96-04 as the alarm came on again and stayed on for more than 7 days in December 1996, and in March 1997. Also, in response to a staff request during a teleconference, the licensee fumished additional information in June 1997 and July 1997 (Refs. 5 and 6).
EVALUATION The staff's previous safety evaluation (Ref. 3) related to the GWL monitoring. The licensee had analyzed the RBs of Units 1 and 2 and qualified them for a maximum GWL of 760 feet msl without_ adverse effects from lateral pressures, uplift, or overtuming due to buoyancy. Although the DG8s were not specifically designed for lateral pressures due to hydrostatic loading caused by the GWL of 760 feet msl, they were designed for loading cases that exceeded the groundwater loadings. The DGBs were analyzed for uplift and overtuming due to buoyancy and were found to be safe for GWL up to 760 feet msl. The AB was analyzed for lateral
i L
- 3 4
pressures, uplift, and overtuming due to buoyancy, and was found safe for hydrostatic loading due to a maximum GWL of 760 feet mal. However, the licensee determined that the governing .'
failure mode of the AB was overtuming due to buoyancy, and that such overtuming would -
require an increase in GWL around the entire perimeter or a large portion of the perimeter of
- the AB to cause overtuming. Elevation 737 feet mal was the maximum level that the .
t groundwater could rise before overtuming would be initiated (Ref.- 3). t h On the basis of this analysis, the licensee committed to maintain groundwater level below 731 feet mal (with a margin of 6 feet below the potential failure limit of 737 feet mal, which is i called the " structural distress" level), and to initiate action to place both McGuire units in Cold Shutdown within 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> after three of the five groundwater alarms are activated at 731 feet l
. mal.
l
\
The rise in the GWL recorded by the monitor at Weli Mk. GWA 2 is only about 1 to 2 inches
- above the setpoint El 731 feet mal, as determined by tt e typical height by which the detector is - ,
' lifted to clear the alarm (Ref. 6). Since the setpoint pastion of 731 feet mal has a margin of 1 6 feet relative to the " structural distress" level of 5 ,; feet mal, and the rise in the level above El 731 feet is minimal, the staff agrees with the licensee's conclusion that there is no safety concem due to the groundwater alarm received at this well.
- l l Even though the small rise in GWL recorded by the non-TS monitor at Well Mk. GWA 2 does not affect the structural integrity of the RB, the staff has examined the reasons given by the F licensee for the rise in the GWL, and reviewed the water table contour plan (FSAR 4
Figure 28 2), a typical section showing the ground surface elevations, and the slope of the i phreatic surface of the groundwater table at the McGuire site (FSAR Figure 2B-3).- On the l basis of this review, the staff agrees with the following conclusions arrived at by the licensee i after its intomal review, performed as part of its corrective action requirements (Ref 5):
i L 1. . The rise in GWL recorded at Well Mk. GWA 2 is a natural phenomenon caused by the rise in the level in Lake Norman and by the increased rainfall in the area. A field survey of the surrounding areas showed no water percolating to the surface which indicates that ,
!: the rise in groundwater level is not due to a pipe break or leak. The alarms at the Well Mk. GWA 2 have been observed to occur whenever the Lake Norman level rose or there !
was substantial rainfall in the area.
- 2. The rise in GWL at Well Mk. GWA-2 is localized, since no alarm was received from any other monitors, indicating the proper functioning of the underground drainage system. ,
' There could be several reasons for M localized phenomenon at Well Mk. GWA 2, such i .,.
~
- as: (1) the local draining of the grourtJwater toward the Unit 2 RB, and (2) the possiba changes in the subsoil characteristics caused by recent constructic, projects near the L Unit 2 side of the site. Further, these projects (e.g., Equipment Staging Building with g caisson foundations) have altered the topography of tha site in this area, allowing more J
4 i
L
. . _ . _ - , - . . . - . - . ~ _ _ . . . - . . - . - . . . _ , . - . - - . - . .- -- .-...- - .- - ., - -.- -- - -- ~ . - - _ . - -
b 4 :
precipitation to soak into the sollinstead of draining into the surface drain system. Ba6ed
- on thoes observations, the resulting small rise of about 1 to 2 inches in the groundwater level at Well Mk. GWA 2 does not jeopardize the safety of the plant or the public, as evidenced by the lack of alarms at any of the TS wells (Ref. 5). Further, the s'.aff agrees with the licensee's proposed action under 10 CFR 50.59 (conveyed to the staff during a -
recent telephone conversation) to set the GWL alarm level at a higher elevation than the
, current level of El 731 feet, but below the structural distress level of El 737 feet to avoid l the frequent activation of the alarm even when the GWL rises only by a couple of inches above El 731 feet.
Si The nearest underground structures, systems, or components are the diesel fuel oil tank and condenser circulating water piping, which are approximately 40 feet away from Well Mk. GWA 2. Based on the distance, the small rise in the groundwater level at Well Mk.
GWA 2 does not affect the safety of any underground structures, systems, or components.
CONCLUSION On the basis of its review of the referenced information, concoming the groundwater level monitoring, the staff is satisfied that the GWL alarm received at Well Mk. GWA 2 near the Unit 2 RB does not pose any safety hazard either for the safety related structures, systems, or components or for the public. Further, the staff agrees with the licensee's proposed action to set the GWL alarm level at a higher elevation than the current level of El 731 feet, but below the '
structural distress level of El 737 feet to avoid the frequent activation of the alarms.
Principal Contributor: R. Pichumani Date: Mar'ch 2, 1998 i
i
__ _ _ . - _ _ ~ _ _ _ . _ _ _ _ _ _ . . _ _ . ... _ _. . . _ _ _ _ _ . . - . _ _
l BidtitDGeE 1
- 1. McGuire Nuclear Station. Units 1 and 2, FSAR Section 2.4.13.5, Design Bases for Subsurface Hydrostatic Loadings, May 14,1996.
- 2. Safety Evaluation Report (NUREG 0422) related to operation of McGuire Nuclear Station, Units 1 and 2, Duke Power Company (DPC), Docket Nos. 50 369 and 50 370, dated r March 1978.
- 3. Safety Evaluation related to Ame.rJment No. 93 to Facility Operating License NPF 9 and Amendment No. 74 to Facility Operating License NPF 17. Duke Power Company, Docket Nos. 50 369 and 50 370, McGuire Nuclear Station, Units 1 and 2, dated March 2,1989.
4
- 4. Letter dated November 14,1996, from T. C. McMeekin, DPC, to NRC, subject: McGuire Nuclear Station, Units 1 and 2, Docket No. 50-369, Special Report No. 96-04, Problem lhvestigation Process No. 2 M96 2898,
- s. Letter dated June 9,1997, from H. B. Barron, DPC, to NRC, subject: McGuire Nuclear Station, Units 1 and 2, Docket No. 50-369, Special Report No. 96-04 Revision 3, Problem Investigation Process No. 2 M96 2898.
- 6. Letter dated July 24,1997, from H. B. Barron, DPC, to NRC, subject: McGuire Nuclear Station Units 1 and 2, Docket No. 50 369, Special Report No. 96-04, Rev. 3, Groundwater Well Mk. GWA 2, Response to Follow up Questions.
I
-