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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20204G3831999-03-19019 March 1999 Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 ML20155B6711998-10-26026 October 1998 Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan ML20154D4401998-10-0202 October 1998 Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 ML20238F3281998-08-31031 August 1998 SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 ML20238F6551998-08-28028 August 1998 SE Authorizing Licensee Request for Relief NR-20,Rev 1 & NR-25,Rev 0 Re Relief from Examination Requirement of Applicable ASME BPV Code,Section XI for First ISI Interval Exams ML20217K6331998-04-20020 April 1998 Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code ML20217K7171998-04-20020 April 1998 Safety Evaluation Accepting Requests for Relief NR-22,NR-23 & NR-24 for First 10-yr Insp Interval ML20216F4921998-03-11011 March 1998 Correction to Safety Evaluation Re Revised SG Tube Rapture Analysis ML20212H1851998-03-0606 March 1998 SE Approving Temporary Use of Current Procedure for Containment Repair & Replacement Activities Instead of Requirements in Amended 10CFR50.55a Rule ML20197B7531998-03-0404 March 1998 SER Accepting License Request for Relief from Immediate Implementation of Amended Requirements of 10CFR50.55a for Plant,Units 1 & 2 ML20199G2591998-01-28028 January 1998 Safety Evaluation Rept Accepting Revised SG Tube Rupture Analysis ML20199H0031998-01-21021 January 1998 SER Accepting Pressure Temp Limits Rept & Methodology for Relocation of Reactor Coolant Sys pressure-temp Limit Curves & Low Temp Overpressure Protection Sys Limits for Byron Station,Units 1 & 2 & Braidwood Station,Units 1 & 2 ML20199C1401998-01-16016 January 1998 SER Accepting Request to Integrate Reactor Vessel Weld Metal Surveillance Program for Byron,Units 1 & 2 & Braidwood,Units 1 & 2 Per 10CFR50 ML20199C1231998-01-13013 January 1998 Safety Evaluation Granting Second 10-yr Inservice Insp Program Plan Relief Request ML20197G0041997-12-11011 December 1997 Safety Evaluation Accepting First 10-yr Interval Insp Program Plan,Rev 4 & Associated Requests for Relief for Plant ML20198H3211997-12-0303 December 1997 Safety Evaluation Re Licensee Submittal of IPE for Plant, Units 1 & 2,in Response to GL 88-02, IPE for Severe Accident Vulnerabilities ML20198R3061997-10-27027 October 1997 Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Process Meets Intent of Subj GL ML20211L2151997-10-0303 October 1997 Safety Evaluation Supporting Licensee Relief Request,Per 10CFR50.55a(a)(3)(i) ML20217C1681997-09-22022 September 1997 Safety Evaluation Accepting Request for Relief from ASME Code,Section Iii,Div 2 for Repair of Damaged Concrete Reinforcement Steel NUREG-1335, Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Associated Guidance, NUREG-13351997-08-28028 August 1997 Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Associated Guidance, NUREG-1335 ML20141L9321997-05-29029 May 1997 Safety Evaluation Accepting Use of ASME Boiler & Pressure Vessel Code,Section Ix,Code Cases 2142-1 & 2143-1 for Reactor Coolant Sys for Plants ML20141B5551997-05-13013 May 1997 SE Accepting First 10-yr Interval Inservice Insp Program Plan Request for Relief NR-29 for Braidwood Station,Units 1 & 2 ML20140H8871997-05-0808 May 1997 Safety Evaluation Supporting Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping Ceco ML20134L7811996-11-18018 November 1996 Safety Evaluation Granting Listed Relief Requests,Per 10CFR50.55a(f)(6)(i) Based on Impracticalities in Design of Valves That Limit IST in Traditional Manner Using Position Indicating Lights ML20129F9101996-10-25025 October 1996 Safety Evaluation Accepting Request to Apply LBB Analyses to Eliminate Large Primary Loop Pipe Rupture from Structural Design Basis for Plant,Units 1 & 2 ML20059E2871993-12-30030 December 1993 Safety Evaluation Supporting Amends 57,57,45,45,93,77,152 & 140 to Licenses NPF-37,NPF-66,NPF-72,NPF-77,NPF-11,NPF-18, DPR-39 & DPR-48 Respectively ML20056D4921993-07-27027 July 1993 Safety Evaluation Re Fuel Reconstitution ML20127N1851993-01-25025 January 1993 Safety Evaluation Accepting Inservice Testing Program for Valves,Relief Request VR-4 ML20059L4581990-09-14014 September 1990 Sser Supporting Util Changes to Inservice Testing Program ML20059L3371990-09-14014 September 1990 SER Granting Interim Relief for 1 Yr or Until Next Refueling Outage to Continue Current Testing Methods While Licensee Investigates Feasibility of Acceptable Alternatives ML20058L9961990-08-0606 August 1990 Safety Evaluation Denying Licensee Response to Station Blackout Rule.Staff Recommends That Licensee Reevaluate Areas of Concern Identified in SER ML20058M0001990-08-0606 August 1990 Safety Evaluation Denying Licensee Response to Station Blackout Rule.Staff Recommends That Licensee Reevaluate Areas of Concern Identified in SER ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20248D5911989-08-0707 August 1989 SER Accepting Util 881130,890411,27 & 0523 Submittals Re Seismic Qualification of Byron Deep Wells ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20247D1471989-07-18018 July 1989 SER Supporting Util Proposed Implementation of ATWS Design, Per 10CFR50.62 Requirements ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20244D8191989-06-13013 June 1989 SER Supporting Util ATWS Mitigating Sys Actuation Circuitry Designs ML20245J0751989-04-25025 April 1989 Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20247B3281989-04-24024 April 1989 Safety Evaluation Re Mechanical Draft Cooling Tower Tests ML20244A7221989-04-11011 April 1989 Safety Evaluation Concluding That Rev 1 to First 10-yr Interval Inservice Insp Program Plan Constitutes Basis for Compliance w/10CFR50.55a & Tech Spec 4.0.5.Response to Items 2.2.2 & 2.2.3 of Inel Technical Evaluation Rept Requested ML20205Q5761988-10-31031 October 1988 SER Re Application for CP for Alchemie Facility-2 Oliver Springs.Licensee Technically Qualified to Construct & Operate Proposed Facility in Such Way as to Assure Adequate Protection for Common Defense & Security 1999-09-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206R6991999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205P7001999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20204G3831999-03-19019 March 1999 Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function1999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20206A8831999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function 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 ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20204C7671999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20202F6181998-12-31031 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function 1999-09-30
[Table view] |
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' EfiCLOSURE-1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
- ENVIRONMENTAL EFFECT5 0F HIGH ENEPGY LINE BREAKS IN THE AUXILIARY STEAM OR STEAM GENERATOR BLOWDOWN SYSTEMS BYRON STATION, UNITS 1 AND 2, BRAIDWOOD STATION, UNITS 1 AND 2 COMMONWEALTH EDISON CO.
DOCKET N05. 50-454/455/456 AND 457
- 1. Background By letter dated May 17, 1985, Commonwealth Edison Co. (CECO), the licensee for Byron 1 informed the staff of revised environmental parameters resulting from a high energy line break (HELB) in the Auxiliary Building, in either the Steam Generator Blowdown (SD) or Auxiliary Steam (AS) System. Postulated breaks in these systems were found to have a greater potential effect on environmental conditions than originally predicted. If a break is not isolated within thirty minutes, equipment qualification temperatures could be exceeded.
The licensee further advised in the May 17, 1985 letter, that modifications were in progress to install temperature sensors at strategic locations to detect a temperature rise due to the local effects of a HELB. A signal from the sensors would initiate automatic closure of an isolation valve in the affected line, thus terminating the break flow. Design, procurement, installation and testing of the modifications was to be completed by August 31, 1985. As an interim measure for continued plant operation, CECO committed to post a watch at locations where breaks could occur. In such an event, the watch personnel would communicate with the control room for operator action to immediately close either the SD containment isolation valves or isolate the AS supply line.
8702170353 870206 PDR ADOCK 05000454 P PDR
By letter dated May 20, 1985 the staff accepted the interim measures until August 31, 1985 (when the permanent modifications were to be completed). In addition it was requested that CEC 0 submit the details of the modifications for staff review.
By letter dated August 2, 1985, CECO submitted a technical description of the permanent modifications at Byron 1 that would aid in isolating the HELB for the AS or SD systems in the Auxiliary Building. They also advised that similar modifications, dependent on break location, would be made on Byron Unit 2 and Braidwood, Units 1 and 2 prior to their fuel load dates.
By letter dated August 23, 1985, CECO advised of installation problems because of equipment interference and delays in delivery of temperature sensors. A completion date for the modifications was _ forecast to I&E to be no later then September 30, 1985. By letter dated August 27, 1985, the staff accepted the schedule, provided personnel were kept posted at locations where breaks could occur.
By letter dated December 11, 1985 CECO responded to a staff request for addi-4 tional information and also advised of additional modifications that were included due to accommodate postulated single active failures. A rescheduled ,
l completion date for Byron. Unit I was set at February 28, 1986.
l By letter dated April 29,1986 CEC 0 provided additional information with regard j to the proposed modifications.
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- , 1 The licensee has' also stated that the modifications had been completed.on Byron, Unit 1, and would be completed prior to fuel load on Byron, Unit .2 and Braidwood, Units 1 and 2. .
'2. Evaluation I
Th'e staff evaluation of the adequacy of the modifications to isolate HELBs and
~
prevent Auxiliary Building temperatures from exceeding equipment qualification 4
temperatures is based on an audit review as prescribed in Standard.. Review Plan-(SRP) 3.6.1. It includes a review of the design of the AS and SD systems l
to assure conformance with the requirements of GDC 4.
i 1
CEC 0 has advised that a temperature of 1400F is the minimum envelope-temperature for equipment qualification in the Auxiliary Building. The modifications for isolating a high energy line break in the AS and SD systems to prevent environ -
0 mental temperatures from exceeding 140 F in the Auxiliary Building consist of:
)
' a) temperature sensors mounted in potentially affected areas (but' not too close to the affected equipment), b) provisions for automatic is61ation of the systems isolation valves, c) control room alarms and d) appropriate procedures. j l
i- CECO has further advised that the temperature sensors and wiring locations in relationship to HELB locations will not be affected by jet impingement. In j addition, only 1E instrumentation will be used. The staff finds this acceptable.-
i, t Details of the staff's evaluation of high energy line breaks in the Auxiliary--
l Steam System and the Steam Generator Blowdown System are discussed below, i !
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e
., 4 Auxiliary Steam (AS) System-
. Auxiliary boiler steam or main turbine extraction steam are supplied to the AS system. The AS system provides low pressure steam to various Auxiliary Building loads which include the boric acid and radwaste systems. A tie line allows for the_ interconnection ~of Units 1 and 2.
In the vicinity of postulated break locations-in the Auxiliary Building where break effects may not be confined to non-safety areas, the. licensee has installed redundant temperature sensors. At a setpoint of 140 F the sensors will initiate a) an alarm in the control room and b) automatic
- s isolation of the AS system from the ~ Auxiliary Building by closure of the parallel, pressure regulating valves AS6i3 and AS167.
To assure that steam flow is isolated in the event of failure of either of these valves, the licensee stated in,the August. 2,1985 letter, that .
- / '
procedures were being developed to require local rnnual closure of valve
~
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A5012 upon receipt of a control room alarm. ,This valve is positioned
- i upstream and in series with valves AS013 and AS167. By letter of i l
December 11, 1985, in response .to a staff inquiry, CECO advised that
~
sufficient time for manual operator action may not be available in the event of a single failure of either of valves AS013 or AS167, and a
stated that further modifications would be made. By letter dated April 29,1986 the 1(chnsee comitted to install'a redundant automaticisolationsalve(AS286) downstream,inserieswith' valves l 1
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AS013 and AS167. The location of the isolation valves assures that upon a HELB, auxiliary steam from both the affected unit and unaffected unit (via the crosstie) is isolated.
The staff finds that the licensee has provided adequate, redundant isolation valves to assure isolation of the AS system in the event of a HELB. This will assure that the Auxiliary Building temperature-will not exceed equipment qualification temperatures.
4 The SD system contributes to maintaining proper water chemistry in the steam generators. Each unit's steam generators blowdown to a condenser located in the Auxiliary Building. A crosstie between Units 1 and 2 allows for the blowdown of all steam generators to one blowdown condenser. This may be desired during maintenance.of a blowdown condenser.
In the vicinity of postulated break locations in the Auxiliary Building where the break may affect safety related equipment, the licensee has 0
installed redundant temperature sensors. At a setpoint of 140 F these sensors will initiate: a) an alarm in the control room and b) automatic isolation of the SD system of the Unit with the activated sensors. In
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response to staff questions the licensee by letters dated December 11 1985'and April 29, 1986 committed to install redundant automatic.
isolation valves'in each steam'generatod blowdown line. This will assure that in the event of a HELB, concurrent with a single active
~
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t failure, the SD system will"be isolated, and prevent' Auxiliary
> Building temperat!ures from exceeding equipment qualification-( temperatures. '
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Automatic isolation of the SD system may not occur, however, if the
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crosstle betwee'n units is being used. For example, in the event of a HELB in one unit,. temperature sensors will only initiate isolation of, s the affected unit's SD system; the unaffected Unit's SD system could l
W feed the break via the crosstie. In response to a staff inquiry re-garding this, CEC 0 by ictter dated April 29, 1986, committed to revise HELBproceduresinvolvingftheSDsystem. Now, upon control room '
annunciationofaO40Fcondition,anoperatoroftheaffectedunitwill verify the crosstie valve positions. If open, operator action.will be 1 ' required at iihe main control board to close the automatic isolation l
. 1 valves of the unaffected' unit's steam generator blowdown lines.
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The staff finds that CEC 0 has provided adequate redundant isolation s
valves and' procedures to assure isolation of the SD systen in the
.\ 9
\ l 5 event of a HELB, thus preventing Auxiliary Building temperatures in
's m\ excess of equipment qualif bation temperatures.
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- 3. Conclusion CEC 0 provided for staff review, information concerning plant modifications
~
and ~ procedures to prevent the qualification temperatures of safety related equipment located in the Auxiliary' Building from being exceeded, in the event of a high energy line break in'either the SD or AS systems.
The staff concludes that the designs of the AS and SD systems for protection against postulated piping failures in the Auxiliary Building, are acceptable, and meet the requirements of GDC 4 with respect to accommodating the effects of postulated pipe ruptures.
l l
.