Rev 2 to Rept on Investigation Performed to Determine Unit 1 Dependence on Unit 2 Sys,Structures & ComponentsML20094B024 |
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Site: |
Grand Gulf |
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Issue date: |
07/17/1984 |
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From: |
Black K MISSISSIPPI POWER & LIGHT CO. |
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To: |
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Shared Package |
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ML20094A990 |
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References |
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84-M-004, 84-M-004-R02, 84-M-4, 84-M-4-R2, NUDOCS 8408060200 |
Download: ML20094B024 (6) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20138A2041997-03-31031 March 1997 Pre-SALP Rept for SALP Period 960225-970906 ML20199G7191997-01-28028 January 1997 Rev 0 to Grand Gulf Nuclear Station Engineering Rept GGNS-97-0002 for GL 96-06 Evaluation of Drywall & Containment Penetrations ML20141A1321996-07-31031 July 1996 Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr ML20115A5851996-06-20020 June 1996 GGNS Engineering Rept for Evaluation of Ampacity Deratings for Thermo-Lag Fire Barrier Encl Cables in Fire Areas/Zones OC214,OC302,OC308 & 1A539 ML20108D0861996-04-30030 April 1996 Surveillance Specimen Program Evaluation for Grand Gulf Nuclear Station ML20115A5831996-04-18018 April 1996 Engineering Rept for Evaluation of Ampacity Deratings for Thermo-Lag Fire Barrier Encl Cables in Fire Areas/Zones OC202,OC402,OC702 & 1A316 ML20100J8621996-02-22022 February 1996 Engineering Rept Safety/Relief Valves Safety Function Lift Setpoint Tolerance Relaxation Summary Rept ML20094M5241995-11-20020 November 1995 Self Assessment SALP Period 940227-960224 ML20078S1351995-02-0808 February 1995 SWS Operational Performance Insp (Swsopi) for Ggns ML20072C9891994-04-30030 April 1994 Survey of Melcor Assessment & Selected Applications, Third Draft ML20063H7791993-12-31031 December 1993 1993 Self Assessment ML20046A2601993-06-18018 June 1993 Safety Sys Functional Assessment, Low Pressure Core Spray & RCIC Sys. ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20116K8001992-11-13013 November 1992 Quarterly Status Rept for Period Ending 920930, 'Degraded Core Accident Hydrogen Control Program.' ML20095K0951992-04-30030 April 1992 Resolution of High Groundwater Levels at Grand Gulf Nuclear Station ML20086K4741991-10-31031 October 1991 Cycle 6 Plant Transient Analysis ML20086K4991991-10-31031 October 1991 Cycle 6 Reload Analysis ML20086K5111991-10-31031 October 1991 LOCA Analysis for Single Loop Operation ML20086K5191991-10-31031 October 1991 Nonproprietary Siemens Nuclear Power Corp Grand Gulf Unit 1 Reload XN-1.3,Cycle 4 Mechanical Design Rept Suppl 1 ML20029C3461991-03-31031 March 1991 Simulator Certification Rept for Grand Gulf Nuclear Station. ML20073K8451991-03-31031 March 1991 Entergy Nuclear Performance Rept,Mar 1991 ML20043B6871990-03-31031 March 1990 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Jan-Mar 1990 ML19353B1281989-12-0101 December 1989 Number 1 Low Pressure Turbine Rotor Ultrasonic Insp Summary. ML19332D1691989-09-30030 September 1989 Quarterly Status Rept for Jul-Sept 1989 Degraded Core Accident Hydrogen Control Program. AECM-89-0165, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 8906301989-06-30030 June 1989 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 890630 ML20235X2621989-02-28028 February 1989 Criticality Safety Analysis of Grand Gulf Nuclear Station Unit 1 Spent Fuel Storage Racks W/Gaps in Neutron Absorbing Panels ML20235N3271989-02-22022 February 1989 Rept on Evaluation of Torsion Shear Stress Components in Design of Pipe Supports ML20247B1901988-11-30030 November 1988 Revised Flow Dependent Thermal Limits AECM-88-0021, Degraded Core Accident Hydrogen Control Program, Quarterly Rept Covering Period 871031-12311987-12-31031 December 1987 Degraded Core Accident Hydrogen Control Program, Quarterly Rept Covering Period 871031-1231 AECM-87-0163, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Apr-June 19871987-08-27027 August 1987 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Apr-June 1987 ML20065N4861987-04-30030 April 1987 Flux Wire Dosimeter Evaluation for Grand Gulf Nuclear Power Station,Unit 1 ML20214U1711987-03-31031 March 1987 Technical Rept 86.2GG, Verification of Individual Plant Evaluation for Grand Gulf. W/Jr Siegel 870313 Release Ltr AECM-87-0102, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending on 8703311987-03-31031 March 1987 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending on 870331 AECM-87-0015, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 8612311986-12-31031 December 1986 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 861231 ML20213G2221986-11-10010 November 1986 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 860930 ML20151A8791986-09-30030 September 1986 Rev 1 to SPDS Safety Analysis ML20215L2311986-09-30030 September 1986 Rev 0 to Grand Gulf Nuclear Station Safety Relief Valve Fatigue Evaluation ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20199L1091986-04-0303 April 1986 Station Blackout Evaluation Rept,Grand Gulf Nuclear Station ML20207G6991986-03-31031 March 1986 Feedwater Heaters Out-of-Svc Analysis,Grand Gulf Units 1 & 2 ML20155B0911986-02-28028 February 1986 Single Loop Operating Analysis ML20205J7381986-02-18018 February 1986 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 851231 ML20141N8871986-02-13013 February 1986 Metallurgical Evaluation of Recirculation Piping Ctr Cross Surface Cracking Following Induction Heat Stress Improvement,Grand Gulf Nuclear Station - Unit 1, Final Rept L-09-100, Rev 0 to MPL-09-100, Grand Gulf In-Plant Safety Relief Valve Test Fatigue Evaluation Final Rept1986-01-31031 January 1986 Rev 0 to MPL-09-100, Grand Gulf In-Plant Safety Relief Valve Test Fatigue Evaluation Final Rept ML20137E4471985-11-19019 November 1985 Metallurgical Evaluation of Recirculation Piping Ctr Cross Surface Cracking Following Induction Heat Stress Improvement,Grand Gulf Nuclear Station - Unit 1, Interim Rept 1999-04-30
[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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- Attachment to AECM-84/0376 LER 84-031-1 Page 3 of 8 REPORT ON INVESTICATION PERF0PJ:ED TO DETERMINE UNIT 1 DEPENDENCE ON UNIT 2 SYSTEMS, STRUCTURES, AND COMPONE;IS REPOP.T NO. 84-M-004 REV. 2 JULY 17, 1984 Prepared By:
E inee -.n upervisor Reviewed By: 7
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- F rincipal Mechani, cal En ineer
.,.cE'P'8lbil' Principal Liectrical Engineer t~< 9.1%dL P ncipal Civil Engin r 8 ~
Approved By: h ..
rector of N lear lineering and Constru to 8400060200 840727 g PDR ADOCK 05000416 8 PDR
l Attachment to AECM-84/0376 LER 84-031-1 Page 4 of 8 INTRODUCTION This report describes the methodology and results of a combined Mississippi Power and Light (MP&L)/Ceneral Electric (GE)/Bechtel design review to identify Grand Gulf Nuclear Station (GGNS) Unit i functions which are dependent on Unit 2 systems, equipment, or structures. Since GGNS was designed as a two unit plant, some facilities were designed as independent systems and structures, while others were designed as common or " shared" items to be utilized by both units.
MP&L recently identified a substantial safety hazard condition requiring the use of nonoperational Unit 2 Standby Service Water (SSW) pumps to transfer water between the SSW basins under postulated accident conditions. The Final Safety
{ '
Analysis Report (FSAR) considered the ability to use the SSW pumps (Q1P41C001A &
B and Q2P41C001A & B) for transfer capabilities in the safety analysis. The pumps are divisional 17 separated in accordance with Regulatory Guide 1.75.
However, the Unit 2 SSV pumps are not operational at this tine and, when con-sidering a LOCA coincident with a single active failure (loss of a division) and loss of offsite power, the ability to transfer Vater between the basins.would be lost during Unit 1 only operation. The SSW basins were designed and constructed as a shared system, to be utilized by and service both units. The root cause of the condition in this interfacing system was that we f ailed to take into consideration single failure criteria with Unit 2 equipment not available.
Consequently, the Nuclear Regulatory Commission (NRC) questioned the readiness of the plant to support Unit 1 operations, and MP&L initiated an investigation to identify all interfaces between CCNS Units (shared systems id/or Unit 2 dependencies) that could effect the safe operation of GGNS Unit 1. The results of this review would then utilized to verify the functionality of all equipment required for Unit 1 operability.
MP&L, GE, and Bechtel have completed this review and con luded that all struc-tures, systems, and equipment required for the safe operation of Unit 1 are ecmplete and functional. The investigation included a review of all non-safety related facilities as well as all safety related structures and systems. The coordinated interdisciplinary review utilized qualified personnel from the Plant Staff, GE, Bechtel, and Nuclear Plant Engineering (NPE). The documentation reviewed includes the FSAR, " upper tier" design drawings such as P& ids and one-line electrical diagrams, design change packages, and temporary alterations.
The detailed methodology and results are presented in subsequent sections and attachments, and figures.
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Attachment to AECM-86/0376 LER 86-031-1 Page 5 of 8 DISCUSSION OnJune4,1984hMP&LdirectedCEandBechteltoinitiatereviewstoidentify Unit 1/ Unit 2 interface dependencies similar to the SSW problem which would require Unit 2 facilities to support the operation of Unit 1.
GE convened an interdisciplinary task force consisting of six senior and principal engineers and managers with expertise in projects, licensing, and mechanical and electrical engineering. The team was intimately familiar with GGNS systems as a result of the recent Technical Specification review effort and previous design efforts.- The 200 man-hour review culminated in the development s
of a candidate list of 28 structures, systems, components, etc. that appeared to l , require Unit 2 equipment to support safety functions associated with Unit 1.
Following detailed discussions with Bechtel, the list was narrowed to four items referred to Bechtel for resolution. The results of the GE review effort are documented in MPGE-84/2-100 (Attachment A).
A 350 man-hour Bechtel review was conducted by 'an interdisciplinary group of approximately twenty senior engineers, group lesders, and discipline engineers associated with the GGNS Unit 1 project. The review was conducted system-by-system or by structure by the Mechanical, Civil, and Electrical / Control disci-plines. Additional review work was performed by the Licensing and Plant Facilities groups. Although discussions with GE focused attention to the list of candidate systems and equipment that appeared to exhibit significant Unit 2 interfaces, the Bechtel review was not limited to these areas. Bechtel reviewed 126 systems, 50 of which were determined to either interface with or to be shared with Unit 2 systems or equipment. Of these 50 systems, four were identified as relying on Unit 2 equipment as described in the summary of the Bechtel review, MPB-84/0256 (Attachment B).
Upon completion of the Bechtel and GE reviews, MP&L sent an engineering review team to both San Jose and Gaithersburg to assess the adequacy of the investiga-
, tions. Each of the two teams consisted of a senior NPE engineer and a staff SRO. Both teams reported that the review efforts were conducted in an organized, thorough, and comprehensive manner. The team reports, including detailed descriptions of the review methodologies employed by GE and Bechtel, are pre-sented in Attachments C and D. However, both the GE and Bechtel reviews were based on their most current in-house documentation which has not been completely updated to include numerous' changes to the plant issued by MP&L. Subsequently, another review effort was initiated to address MP&L Design Change Packages (DCP's) and Temporary Alterations to determine if additional dependent inter-faces with Unit 2 had been created. The overall review effort is diagrammed on Figure 1.-
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Attachment to AECM-84/0376 LER 84-031-1 Page 6 of 8 FOLL0k'UP MP&L ACTIONS Eight Bechtel engineers from the initial review group traveled to the plant site to conduct a review of DCP's associated with Unit I systems determined to interface with Unit 2. Several additional Balance of Plant (BOP) systams interfacing with Unit 2 were identified by MP&L. These systems and associated DCP's were revicwed by the Bechtel team. In the Bechtel followup review DCP's associated with a Unit 2 interface involving a safety function were reviewed to identify any dependence on Unit 2 equipment. This review is documented in NPEI 84/1024 (Attachment E) included in Attachment E is an example review sheet.
Concurrently, MP&L/NPE engineers reviewed DCP's associated with Unit I systems f-without Unit 2 interfaces to confirm that no new interfaces had been created.
The MP&L review is documented in NPEI 84/1025 (Attachment F) also included in Attachment F is an example review sheet. Similarly, Plant Staff conducted a review of all open Temporary Alterations as discussed in PMI 84/7151 (Attachment G) included this attachment is an example review sheet.
The review is diagrammed on Figure 2.
Due to questions raised by the MP&L Safety Review Committee on July 12, 1984, relative to the resolution of the Unit 1/ Unit 2 interfaces identified by GE in MPGE-84/2-0100, MP&L directed Bechtel to document how each item was resolved along with its resolution. In addition, Bechtel was directed to provide the same information on the systems with the Unit 2 interface as previously iden-tified by Bechtel. The method used by Bechtel to accomplish this effort along with the results are presented in Attachment H (MPB 84/0303).
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Attachment to AECM-84/0376 LER 84-031-1 Page 7 of 8 RESULTS CE has determined that the primary NSSS systems have no direct Unit 2 interde-pendencies. However, in the remainder of the plant, four significant areas (Items 1-4) were identified by Bechtel as relying on Unit 2 equipment along with Items 5 and 6.
- 1. Standby Service Water System (P41) - Unit 2 SSW pumps are required to transfer water from one SSW basin to the other in the event of a postulated LOCA in Unit 1. The associated ventilation system, Y47, is also required.
With the completion of the SSW siphon work (DCP 84/5006), all equipment
- required to support these interfaces is functional.
- 2. Instrument Air System (P53) - The Unit 2 instrument air compressor has been made operable on Unit 1 B0P power as a backup to the Unit I compressor to improve reliability during normal plant conditions. The instrument air system is not safety related.
- 3. Safeguard Switchgear and Battery Room Ventilation System (Z77) - The Unit 2 equipment has been dedicated for use on and powered from Unit 1. It has undergone preoperational testing and has been turned over to FT&L for use.
- 4. SSW Pumphouse Ventilation System (Y47) - The Unit 2 ventilation system in SSW basin A is required during operation of the Unit i HPCS service water pump in the event Unit 1, Division I, power is unavailable. The Unit 2 equipment has undergone preoperational testing and has been turned over to MP&L for use. It is powered from Unit 1, Division II.
- 5. The DCP/ Temporary Alternation review uncovered one additional dependence.
Doors 2M110 and 2M111 and penetration 2SJ-8A in the SSW basin B are required by DCP 82/5026 to be sealed to protect Unit i equipment from flooding resulting from revised PMP studies.
- 6. 500 KV Switchgear (R27) - Original design for AC auxiliary power for 500 kv Switchgear constitutes three 100% capacity transformers fed from breakers 152-1610. 152-1905 and 152-2610. Breakers 152-1610 and 152-1905 are Unit i equipment and each capable of supplying full requirement. Therefore, without Unit 2 breaker 152-2610 the switchgear has two (2) redundant 100%
capacity power sources. We are, however, transformed 100% capacity 13.8 KV - 480 v temporary station service power to a permanent installation so that switchgear operation will not require any revision.
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Attachm:nt to AECM-84/-0376 LER 84-031-1 Page 8 of 8 CONCLUSIONS In the design of the two-unit GGNS plant, shared systems have been designed and constructed as Unit I systems. Based on the results of the reviews discussed in this report, N?E ccncludes that the problem associated with the nonoperational Unit 2 SSW pumps was an isolated, unique situation and that Unit I can be safely operated, having cortected that problem.
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