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Category:ANNUAL OPERATING REPORT
MONTHYEARML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20217A1191997-12-31031 December 1997 Summary Description of Facility Changes,Tests & Experiments, Including Summary of Ses,Conducted During 1997 ML20137C4071996-12-31031 December 1996 Summary of Facility Changes,Tests & Experiments for 1996 ML20101C7181995-12-31031 December 1995 Summary of Facility Changes,Tests & Experiments During 1995 ML20081K9711994-12-31031 December 1994 Summary Description of Facility Changes,Tests & Experiments, Including Summary of Safety Evaluations Conducted at North Anna Station During 1994,per 10CFR50.59(b)(2) ML20064P0921993-12-31031 December 1993 Summary of Facility Changes,Tests & Experiments for 1993 for North Anna Power Station Units 1 & 2 ML20012E2191989-12-31031 December 1989 Summaries of 10CFR50.59 Changes North Anna Power Station. W/900320 Ltr ML20248B2981988-12-31031 December 1988 Summary of Procedure Changes,Facility Changes & Special Tests Per 10CFR50.59. Summary of Safety Evaluation for Each Procedure Change,Facility Change & Special Test Included ML20151A8271987-12-31031 December 1987 Summary of Procedure Changes,Facility Changes & Special Test for 1987 ML20206A6151987-04-0101 April 1987 Summary of Facility Changes,1986 ML20205T5581987-04-0101 April 1987 Annual Operating Rept for 1986,consisting of Summary of Procedure Changes & Special Tests ML20003E9431981-04-13013 April 1981 Summaries of Facility Design Changes & Special Tests Completed During 1980 ML19323G9331980-06-0505 June 1980 Special Tests & Design Changes 1979. 1998-12-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206H0221999-05-0303 May 1999 Informs That Licensee Changes Bases for TS 3/4.6.1.2, Containment Leakage. Changes Allow Use of Other NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing.Ts Bases Page,Encl ML20206G9481999-05-0303 May 1999 Informs NRC That Insp of 58 Accessible safety-related Pipe Supports Completed in Response to NOV from Insp Rept 50-338/98-05 & 50-339/98-05.Commitments Made Include Plans to Perform Assessment of Welding & Welding Insp ML20205T1181999-04-16016 April 1999 Requests NRC Approval Prior to Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit.Nrc Concurrence with Irradiation Program Requested by End of June 1999 ML20205P1891999-04-0808 April 1999 Forwards ISI Program for Third ten-yr ISI Interval for North Anna Unit 1 for Class 1,2 & 3 Components & Component Support.Third ten-yr Insp Interval for North Anna Unit 1 Begins on 990501.Page 2-26 of Encl Not Included ML20205K3631999-04-0505 April 1999 Requests That Relief Request IWE-3 Be Removed from 980804 Relief Requests Submitted to Nrc.Subject Relief Request Was Inadvertently Retained in Attachment 1 for Unit 1 ML20205K2191999-04-0101 April 1999 Forwards Response to NRC 990106 RAI Re Util Summary Rept on USI A-46 Program,Submitted 970527.Calculations & Corrected Table 11.1-1,encl ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML20205E2701999-02-25025 February 1999 Forwards Rept on Status of Decommissioning Funding for North Anna Power Station,Units 1 & 2.Trust Agreement Between Old Dominion & Bankers Trust Co,Effective 990301,attached ML20207A8741999-02-25025 February 1999 Draft Response to NRC Telcon Re Licensee Request for Approval of LBB Evaluation in Support of Elimination of Augmented Insp Program on RCS Loop Bypass Lines.Response Justifies Use of Less than One Gpm Detectable Leakage Rate ML18152B5401999-02-11011 February 1999 Requests Relief from Specific Requirements of Subsection Iwl of 1992 Edition with 1992 Addenda of ASME Section Xi,Per 10CFR50.55a(a)(3) ML20203C8181999-02-0505 February 1999 Forwards Response to NRC 981217 Telcon RAI Re risk-basis of Nitrogen Accumulator Action Statement to Complete NRC Review of 951025 Proposed TS Changes 1999-09-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08
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VINGINIA ELucTHIC AND POWER COMi%NY Hicuxoxu,Vinoisir etter,I W.L. STEWART Vacs Pmastommt xectain o,. na== April 1, 1987 United States Nuclear Regulatory Commission Serial No.87-117 Attention: Document Control Desk N0/JHL:jmj Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY j NORTH ANNA POWER STATION UNITS 1 AND 2 SUB9tARY OF PROCEDURE CHANGES AND TESTS PURSUANT TO 10 CFR 50.59 Enclosed is a summary of procedure changes and special tests carried out in 1986 pursuant to 10 CFR 50.59 for North Anna Units 1 and 2, including a summary of the safety evaluation of each.
Very truly yours, I
ke %s W. L. Stewart Attachments 870407 O[$ob330 g
PDR A PDR i
cc: U. S. Nuclear Regulatory Cocutission 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 ,
1 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station l
1 1
.= . ~ . - .
PROCEDURES REQUIRING A SAFETY EVALUATION DURING 1986 EMP-C-BY-2.1: Battery Cell Charging In Groups of 15 or Less SNSOC approved safety evaluation: 4/23/86
Description:
The purpose of this procedure was to allow the capability of charging battery cells in groups of 15 or less.
Description of the Safety Evaluation:
The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the safety analysis report was not increased. The possibility of a different type of accident or malfunction than was previously evaluated in the safety analysis report was not created.
The margin of safety as described in the bases section of any part of the technical specifications was not reduced. The procedure was to allow the new station batteries to receive a freshening charge in accordance with the vendor manual. The battery cells vers to receive a freshening charge in groups of 15 or less in order to obtain battery operability.
SPECIAL TESTS COMPLETED IN 1986 NORTH ANNA POWER STATION 1-ST-1: Steam Generator Moisture Carryover Test SNSOC approved test: 7/24/86 ; 11/13/86 SNSOC approved test results: Unit 1 - 7/24/86 ; 11/13/86 ; 11/26/86 Unit 2 - 7/24/86 ; 11/26/86
Description:
This test measured the effectiveness of the steam generators by quantifying the amount of moisture that is carried with the steam into the turbines.
Description of the Safety Evaluation:
The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the safety analysis report was
. not increased since review has shown no interface with systems involved with reactor safety. The possibility of a different' type of accident or malfunction than was previously evaluated in the safety analysis report was not created since plant operation is not affected by adding Sodium-24 (half life 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />) and taking recondary samples for analysis. The margin of safety as described in the bases section of any part of the technical specifications was not reduced since review has shown no interface with systems involved with reactor i safety and plant operation is not affected by adding Sodium-24 and taking secondary samples for analysis.
1 1-ST-67: Control Room Bottled Air Special Test 1
i SNSOC approved test: 1/31/86 SNSOC approved test results: 4/10/86 i
Description:
The test verified that the control room bottled air system can deliver 340 cfm to the control room and maintain the control room at an average positive
{
pressure greater than or equal to 0.05 inches of water for one hour.
2 Description of the Safety Evaluation:
The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the safety analysis report was not increased since a review of the UFSAR indicated that the accident analyses remained bounding for this test. The possibility of a different type of accident or malfunction than was previously evaluated in the safety analysis report was not created since a review of the UFSAR indicated that the accident analyses remained bounding for this test. The margin of safety as described in l the bases section of any pert of the technical specifications was not reduced.
l The requirements of Techniaal Specification 4.7.7.2b were met.
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1-ST-69: Determination of the EDG Load Limiter 3000kw Setpoint SNSOC approved test: 12/4/86 SNSOC approved test results: 12/18/86 ; 1/15/87
Description:
This test identified the point at which the load limiter on a diesel generator should be set in order to limit the electrical output of the diesel to less than or equal to 3000kw. This test was performed on one Unit I diesel and one Unit 2 diesel in December of 1986.
Description of the Safety Evaluation:
The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the safety analysis report was not increased. The possibility of a different type of accident or malfunction than was previously evaluated in the safety analysis report was not created.
The margin of safety as described in the bases section of any part of the technical specifications was not reduced. The ability of the diesel generators to perform as described in the UFSAR was not affected. The test only marked a spot on the limiter. A physical stop was not installed.
1-ST-70/2-ST-51: Tavg Reduction at Core Uprated Power SNSOC approved test: 11/13/86 ; 12/4/86 SNSOC approved test results: Unit 1 & 2: 12/4/86
Description:
This test reduced RCS Tavg by 10*F, and monitored the effects of the change.
The test was performed to gather data to be used in evaluating the feasibility of permanently reducing Tavg in order to reduce stress corrosion cracking problems in the steam generators.
Description of the Safety Evaluation:
The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the safety analysis report was not increased. The test conditions created only incremental changes in the values of parameters previously known to be significant in determining core response to known accidents. The predicted values of parameters are within the range of existing safety analysis values. The possibility of a different type of accident or malfunction than was previously evaluated in the safety analysis report was not created since the test involved no system changes and the predicted values of parameters are within the range of the existing safety analysis. The margin of safety as described in the bases section of any part of the technical specifications was not reduced. The analyses demonstrated that the calculated results met the acceptance criteria described in the UFSAR.
1-ST-71: Control Room HVAC Test SNSOC approved test: 12/4/86 SNSOC approved test results: 12/4/86
Description:
This test was performed to collect flow balance data on the control room ventilation system.
Description of the Safety Evaluation:
The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the safety analysis report was not increased. The ability of the control room ventilation system to perform as required in the event of a safety injection signal was not affected. The operation of the system was not affected by obtaining flow data. The possibility of a different type of accident or malfunction than was previously evaluated in the safety analysis report was not created. System operation was performed in accordance with the UFSAR. The margin of safety as described in the bases section of any part of the technical specifications was not reduced.
The ability of the control room ventilation system to perform as required in the event of a safety injection signal was not affected. The operation of the system was not affected by obtaining flow data. System operation was performed in accordance with the UFSAR.
2-ST-48: Large Bore Snubber Accumulator System Troubleshooting SNSOC approved test: 2/25/86
, SNSOC approved test results: 4/10/86 (twice)
Description:
This test was performed to document the inspection of the reservoirs and associated piping of large bore snubbers. The snubbers inspected were in the "B" and "C" steam generator cubicles on Unit 2.
Description of the Safety Evaluation:
The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the safety analysis report was not increased. The possibility of a different type of accident or malfunction than was previously evaluated in the safety analysis report was not created.
The test van used to observe the reservoirs of certain large bore snubbers.
The system was returned to its original condition following the test. The margin of safety as described in the bases section of any part of the technical specifications was not reduced. The test did not affect technical specification operability.
A 2-ST-49: 2H Diesel Extended Run SNSOC approved test: 3/20/86 SNSOC approved test results: 2/26/87
Description:
This test was performed on the 2H Emergency Diesel Generator. Its purpose was to monitor the diesels performance during a run over an extended period of time (approximately 130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />). The test also provided instructions for determining the setpoint for the load limiter which corresponds to a load of 3000kw. The test was performed in March, 1986.
Description of the Safety Evaluation:
The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the safety analysis report was not increased. The diesel generator remained fully capable of performing its function during undervoltage conditions, station blackout or safety injection initiation. The possibility of a different type of accident or malfunction than was previously evaluated in the safety analysis report was not created.
Adequate offsite power supplies remained available and the diesel generator was still capable of performing its intended function during the test. The margin of safety as described in the bases section of any part of the technical specifications was not reduced. The diesel generator remained operable during the test.