Interim Deficiency Rept Re Use of Invalid Seismic Amplified Response Spectra in Design of safety-related Components. Contractor Is Redesigning Containment Annular Steel Frame. Contractor 791106 Ltr Re Deficiency EnclML19276H631 |
Person / Time |
---|
Site: |
Seabrook ![NextEra Energy icon.png](/w/images/9/9b/NextEra_Energy_icon.png) |
---|
Issue date: |
12/06/1979 |
---|
From: |
PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
---|
To: |
|
---|
Shared Package |
---|
ML19276H630 |
List: |
---|
References |
---|
NUDOCS 7912120466 |
Download: ML19276H631 (9) |
|
|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20081F6091991-04-23023 April 1991 Part 21 Rept Re Edward Controlled Closure Check Valves & Testable Piston Check Valves Dashplate Bolt Failures Due to Rapid Valve Opening or Impulsive Differential Pressure Surge Across Dashplate.Design Changes Recommended ML20246C0881989-06-21021 June 1989 Potential Significant Deficiency Rept Re Possibility That Atmospheric Dump Valves May Fail to Open.Caused by High Bonnet Pressure Not Permitting Actuator to Open Valve.Plug Should Be Reworked to Enlarge Pilot Flow Area ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20204H1481988-10-14014 October 1988 Final Deficiencty Rept CDR 84-00-13 Re Portions of Control Circuits Not Considered When Evaluating Total Circuit Length for Voltage Drop Calculations.Initially Reported on 840830. Independent Review Confirms Corrective Actions Completed ML20235Y2901987-10-0909 October 1987 Part 21 Rept Re Potential Hazard That Magnet in Class J Industrial Control Relays May Jam When Called to de-energize & Control Circuits May Not Open.Special 120-volt Coil Removed & New Relay Installed ML20214A1361987-05-12012 May 1987 Part 21 Rept Re Capacity of Thermal Compensating Accumulator Being Insufficient to Compensate for Thermal Expansions of Hydraulic Fluid During Full Ambient Temp Transient Required by Customer Specs.Interim & Permanent Mods Identified ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20207J2111986-11-26026 November 1986 Final Deficiency Rept CDR-86-00-09 Re Ambient Temp Compensation Calibr Shifts in Veritrak Group a Transmitters. Initially Reported on 860912.Existing Transmitters Will Be Replaced W/Rosemount Transmitters ML20214R8981986-09-18018 September 1986 Supplemental Final Deficiency Rept CDR 85-00-13 Re Lining Defects in Svc Water Sys.Piping Spool Insp Will Be Performed Immediately Due to Exceeding Originally Anticipated Insp Interval ML20214Q8661986-09-16016 September 1986 Final Deficiency Rept CDR 85-00-20 Re Failure of Fire Damper to Close Under Design Airflow Conditions.Initially Reported on 851206.Calculations to Determine Which Fire Dampers Could Fail Under Dynamic Flow Conditions Taken ML20210F4741986-09-16016 September 1986 Part 21 Rept Re Possible Sticking in Closed or Partially Open Position on Dresser 3050 Diaphragm Valves.Initially Reported on 850118.Disc Caps,Including Chamfers on Outside Diameter,Will Be Modified ML20210F4081986-09-12012 September 1986 Interim Deficiency Rept (CDR 86-00-09) Re Excessive Calibr in Veritrak/Tobar Transmitters.Initially Reported on 860805. Destructive Exam Testing Underway.Nrc Will Be Informed of Status Upon Completion of Tests ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms ML20206U1481986-08-21021 August 1986 Final Deficiency Rept (CDR 81-00-10) Re Inconsistency in Electrical Cable Tray Support Bolts Design.Initially Reported on 810727.Required Mods to Conduit & Cable Tray Support Connections Installed & Inspected ML20203M0271986-08-14014 August 1986 Final Deficiency Rept (CDR 86-00-08) Re Failure to Ensure Adequate Torquing of Cable Tray hold-down Clamps.Initially Reported on 860716.Clamps Retorqued & Installation & Insp Criteria Revised ML20212N0651986-07-25025 July 1986 Final Deficiency Rept CDR 84-00-06 Re Components & Component Supports Spanning Expansion Joints.Initially Reported on 840405.Field Walkdown of All Bldgs Performed & Design Changes Issued to Assure Sys & Structure Integrity ML20204J3131986-07-18018 July 1986 Final Deficiency Rept (CDR-86-00-07) Re Valve Alignment of ECCS During Cold Leg Recirculation Phase of post-LOCA ECCS Operation.Initially Reported on 860606.Low Head Safety Injection Sys Valve Alignment Will Be Used & FSAR Updated ML20212C7501986-07-18018 July 1986 Interim Deficiency Rept CDR 86-00-08 Re Cable Tray Hold Down Clamps.Initially Reported on 860716.Program to Retorque All Cable Tray Hold Down Clamps in safety-related Areas Implemented.Next Rept by 860815 ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20205B3931986-06-30030 June 1986 Final Deficiency Rept CDR-86-00-02 Re Ambient Temp Drift Problem W/Veritrak Pressurizer Pressure Transmitters. Initially Reported on 860307.Tobar Pressurizer Pressure Transmitters Installed ML20212D5191986-06-24024 June 1986 Final Deficiency Rept CDR 86-00-06 Re Westinghouse W-24 Operational Amplifiers.Initially Reported on 860605. Westinghouse Nal Cards Having W-24 Operational Amplifiers W/Dated Code 8101 Replaced ML20211Q2731986-06-16016 June 1986 Final Deficiency Rept CDR 84-00-17 Re Insufficient Fillet Weld Size in Coped Area of Structural Steel I-beams Supplied by Cives Steel.Initially Reported on 841026.Mods Issued & Completed to Ensure Integrity of Structural Member ML20207H4771986-06-13013 June 1986 Final Deficiency Rept CDR-79-00-04 Re Potential Undetectable Failure in P-4 Interlock Circuit of Esfas.Installation of Test Switches & Meters as Recommended by Westinghouse & Procedures for Performing Periodic Testing Completed ML20207H4991986-06-10010 June 1986 Final Deficiency Rept CDR-85-00-18 Re Possible Malfunction of Figure 3050 Diaphragm Valves Supplied by Dresser Industries.Initially Reported on 851023.Caused by Valve Disc Cap Not Allowing Disc to Move.Mods to Disc Guides Complete ML20206F0741986-06-0606 June 1986 Final Deficiency Rept (CDR 86-00-03) Re Potential Malfunction of P-10 Permissive.Initially Reported on 860324. Verification That P-10 Permissive Properly Changes State Will Be Made by Observing Bistable Status Lights ML20211H4071986-06-0606 June 1986 Final Deficiency Rept (CDR 85-00-07) Re HVAC Design Defect. Initially Reported on 850409.Fifteen-ton Chiller Unit Added in Equipment Vault Stairways & Electrical Area Above ML20211H3981986-06-0606 June 1986 Final Deficiency Rept (CDR 85-00-16) Re Gauled Threads on Manual Handwheel Operators on safety-related Dampers Causing Operator & Damper to Seize.Initially Reported on 851017.Mods Recommended by Pacific Air Products Completed ML20211H3841986-06-0505 June 1986 Final Deficiency Rept (CDR 83-00-14) Re Supports for Svc Air Sys & Other Sys Carring non-nuclear Safety Designation. Initially Reported on 830714.Affected Lines Reviewed to Determine If Supports Should Be non-nuclear Seismic (NNS-1) ML20199F5041986-06-0505 June 1986 Interim Deficiency Rept (CDR 86-00-06) Re Excessive Shift of Calibr Trip Setpoints on Westinghouse W-24 Operational Amplifiers.Initially Reported on 860501.Amplifiers Will Be Replaced ML20206F0771986-06-0303 June 1986 Final Deficiency Rept (CDR 86-00-04) Re Potential Malfunction in 25 Kva Inverters Mfg by Elgar Corp Due to Improper Stacking of Cable Lugs.Initially Reported on 860509.Actions Complete for Unit 1 ML20206B7291986-05-28028 May 1986 Final Deficiency & Part 21 Rept (CDR 85-00-17) Re Potential for Gould-supplied Motor Control Starters to Bind or Seize Contact Carrier Assembly.Reinsp Conducted to Ensure That Washers Installed Under Contact Carrier ML20206B8701986-05-28028 May 1986 Final Deficiency Rept (CDR 84-00-13) Re Control Circuit Cable Lengths.Corrective Actions as Specified in Completed.Solutions Involved Rewiring W/Larger Conductors & Reconfiguration of Some Circuits ML20206B8371986-05-20020 May 1986 Final Deficiency Rept (CDR 85-00-04) Re Blocked Air Hose in Vent Lines from safety-related air-operated Actuators. Initially Reported on 850301.Unit 1 Air Hoses Replaced.Unit 2 Hoses Not Yet Installed ML20198N1641986-05-20020 May 1986 Final Deficiency Rept CDR 84-00-05 Re Overstressed Welds That Join Expansion Joint Assemblies to Fuel Transfer Tube. Initially Reported on 840427.Welds Reworked Per ASME III, Code Class 2 Criteria ML20198P3501986-05-20020 May 1986 Final Deficiency Rept CDR 84-00-08 Re Weld Deficiencies on Fisher Controls Valve Operator Bracket Welds.Initially Reported on 840419.Corrective Actions,Including Insp & Repair of Brackets,Completed ML20205R8571986-05-10010 May 1986 Final Deficiency Rept Re Emergency Feedwater Sys Design Flow Requirements.Initially Reported on 860425.Emergency Feedwater Pump Constant Flow Recirculation Line Replaced W/ New Safety Class 3 Recirculation Line for Each Pump ML20215M7181986-05-0909 May 1986 Interim Deficiency Rept (CDR 86-00-04) Re Improper Cable Lug Connections in 25 Kva Inverter.Initially Reported on 860401. Cable Lugs for Dc & Ac Power Supply Connections Will Be Determinated & Properly Reterminated ML20206C2671986-05-0707 May 1986 Interim Deficiency Rept (CDR 86-00-03) Re Potential Malfunction of Reactor Protection Sys Permissive P-10 Function Under Stated Circumstances.Initially Reported on 860324.Corrective Action in Incorporated ML20141E4311986-04-10010 April 1986 Final Deficiency Rept (CRD-85-00-13) Re Failure of Svc Water Sys Spool Linings,Piping Inserts & Valve Liner/Seats. Initially Reported on 850918.At Least One Piping Spool Will Be Removed for Insp of Coating During Each Outage ML20141H9791986-04-10010 April 1986 Interim Deficiency Rept (CDR 86-00-02) Re Veritrak 76PH2 Pressure Transmitters Calibr Shifts.Initially Reported on 860307.Addl Rept Will Follow Upon Completion of Westinghouse Analysis ML20155F3181986-04-0202 April 1986 Final Deficiency Rept (CRD 85-00-11) Re Incorrect Short Time Delay Band Levers on Brown Boveri K-line Circuit Breaker W/ Overcurrent Trip Device.Initially Reported on 850731.Unit 1 Corrective Action Complete.Unit 2 Being Tracked ML20199J8341986-03-31031 March 1986 Final Deficiency Rept CDR 86-00-01 Re Design of Diesel Generator Air Start Sys.Initially Reported on 860220.Colt Industries Reset Electric Governor & Revised Starting Air Design to Vent Booster Air Via Pilot Air Connection ML20199H1741986-03-31031 March 1986 Interim Deficiency Rept CDR 85-00-19 Re Misapplication of Potter-Brumfield Type Mdr Relays.Initially Reported on 851216.Rectifier Assemblies Will Be Added to Circuitry to Convert Ac Back to Dc to Operate Dc Solenoid Valves ML20199G4561986-03-31031 March 1986 Interim Deficiency Rept (CDR 85-00-17) Re Binding of Contact Carrier Assembly in Gould Motor Control Starters.Initially Reported on 851118.Affected Starters Will Be Replaced or Modified ML20210E5661986-03-0606 March 1986 Interim Potential Deficiency Rept CDR 85-00-20 Re Failure of Fire Damper to Close Under Design Airflow Conditions. Initially Reported on 851206.Final Rept Will Be Submitted When Corrective Actions Completed ML20141N6251986-03-0505 March 1986 Final Deficiency Rept CDR-83-00-10 Re Westinghouse 7300 Process Protection Sys Ntc Card Relays.Initially Reported on 830617.Modified Ntc Printed Circuit Card Installed as Solution to Mercury Wetted Relay Contact Bounce Problem 1997-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H2841999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Seabrook Station. with ML20212D1461999-09-17017 September 1999 SER Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20212B8671999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Seabrook Station. with ML20210Q7581999-08-11011 August 1999 SER Approving Proposed Merger of CES & Bec,Which Will Create New Parent Company of Canal ML20210R9781999-08-0606 August 1999 ISI Exam Rept of Seabrook Station, for RFO 6,period 3 ML20210J8681999-08-0303 August 1999 SER Approving License Transfer from Montaup Electric Co to Little Bay Power Corp & Approval of Conforming Amend for Seabrook Station Unit 1 ML20210R6001999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Seabrook Station, Unit 1.With ML20210H1151999-06-30030 June 1999 Naesc Semi-Annual Fitness-for-Duty Rept for 990101-0630 ML20209H1371999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Seabrook Station, Unit 1.With ML20195G5391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Seabrook Station, Unit 1.With ML20195C0491999-05-25025 May 1999 Offshore Intake Seal Deterrent Barrier Design ML20206E4761999-04-30030 April 1999 LER 99-S01-00:on 990408,contractor Employee Was Granted Temporary Unescorted Access to Seabrook Station Protected Area.Caused by Failure of Contractor Employee to Provide Accurate Info.Individual Access Revoked.With ML20206N1751999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Seabrook Station, Unit 1.With ML20196L2081999-04-19019 April 1999 Rev 01-07-00 to RE-21, Cycle 7 Colr ML20205K5441999-03-31031 March 1999 Decommissioning Update ML20205L8141999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Seabrook Station. with ML20205C1981999-03-24024 March 1999 Safety Evaluation Concluding That Proposed Relief Request IR-8,Rev 1,provides Acceptable Alternative to ASME Code Requirements.Recommends Authorization of Proposed Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20207F4941999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Seabrook Station. with ML20199E6731998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Seabrook Station, Unit 1.With ML20198P1831998-12-31031 December 1998 LER 98-S01-00:on 981214,incomplete pre-employment Screening Records Was Noted.Caused by Failure of Contractor Employee to Provide Accurate Info.Subject Contractor Employees Employment Was Terminated.With ML20202E8241998-12-31031 December 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980701-981231 ML20196F5741998-12-0202 December 1998 Safety Evaluation Concluding That Licensee Has Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Seabrook ML20198B8661998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Seabrook Station, Unit 1.With ML20195D0311998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Seabrook Station, Unit 1.With ML20154H5291998-10-0808 October 1998 Special Rept:On 980928,meteorological Monitoring Instrumentation Channel Inoperable for Period Greater than 7 Days.Caused by Vendor to Follow Std Industry Practice for Calibr of Instrumentation.Instruments Installed ML20154M8421998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Seabrook Generating Station,Unit 1.With ML20151V5951998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Seabrook Station, Unit 1.With ML20237B4501998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Seabrook Station ML20236R1781998-06-30030 June 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980101-0630 ML20236M3591998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Seabrook Station, Unit 1 ML20237A4871998-06-0303 June 1998 North Atlantic Seabrook Station 1998 Exercise on 980603 ML20248M2951998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Seabrook Station, Unit 1 ML20247G2641998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Seabrook Station ML20247H3171998-04-27027 April 1998 Rev 1 to Seabrook Station SGs B & C Isi,May/June 1997 ML20216F8891998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Seabrook Station 05000443/LER-1998-002, Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted1998-03-20020 March 1998 Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted ML20216H9211998-03-13013 March 1998 Fitness for Duty Program Performance Data Personnel Subject to 10CFR26 ML20248L2811998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Seabrook Station, Unit 1 ML20197A7531998-02-27027 February 1998 Safety Evaluation Accepting License Request for Relief from ASME Code,Section IX Requirements Re Inservice Insp of RHR Heat Exchanger Nozzle Welds & Reactor Vessel Closure Head Nuts ML20202G3701998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Seabrook Station ML20198G0271997-12-31031 December 1997 Commonwealth Energy Sys 1997 Annual Rept ML20248L7711997-12-31031 December 1997 Western Massachusetts Electric 1997 Annual Rept. Supporting Info,Encl ML20198G1021997-12-31031 December 1997 Baycorp Holdings 1997 Annual Rept ML20198N7021997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Seabrook Station, Unit 1 ML20198G0351997-12-31031 December 1997 Eastern Edison Co 1997 Annual Rept ML20198G0681997-12-31031 December 1997 Taunton Municipal Lighting Plant 1997 Annual Rept ML20248L7671997-12-31031 December 1997 North Atlantic 1997 Annual Rept ML20198F9511997-12-31031 December 1997 United Illuminating Co 1997 Annual Rept ML20236M9561997-12-31031 December 1997 Amended Public Service of New Hampshire 1997 Annual Rept 1999-09-30
[Table view] |
Text
. _ . _ __ . . _ _ _ . _ ._ . , ,
O Public Service Company of New 11ampshire Scabrook Starion Interim Report en Use of Invalid Scismic A:aplified Response Spectra Date: Decc:abe r o , 1979 M
i 7 912120 yhd ,
i Scabrook Proicct Inticim Report on Use of Invalid Seismic Amnlified Resnense Snectra Introduction on Tuesday, November u, 1979, Mr. J. Devincentis, Seabreak Project Manager for Yankee Atomic Electric Company, . reported by teleritanc to Mr. J. Mattia, NRC Region I Inspection and Enforcement inspector for the Seabrook Project, two significant design deficiencies under 10 CFR50.55(c). YACC had that same day received written aotice of the two deficiencias from the Scabrook architect-enginecr-construction manager, United Enginects & Constructors Inc., under UESC letter numbers SBU-31426 and SCU-31428.
The purpose of this report is to provide in t e ria, infarination ca one of those reported deficiencies; namely, that identified ta SEL'-31426 (sce Attachment 1) involving the use of incorrect seismic amplified response spectra (ARS) in the 'ign of components supported by the containment building annular steel frame.
Structural Descriotion of Containment Bui. ld iut; For plans and clevation arrangements of the Seabrook containment building internals, refer to Seabrook PSAR Figures 1.2-2 through 1.2-6.
We following is a brief description of the Seabrook contaituaent building and tis internal structures:
S Y*
G 1
.' . . - . s 2
Structural Description of Containment I:n i Id i ne. (Co n t ' d )
The Containment Shell is a reinforced concrete cyllader eita an he:.:L-spherical dome, both lined with carbon steel plate. Se contain:nent con-crete internals consist of the pritaary and secondary shield vallu, support-ing columns for the gantry cranc, the refueling caaal and ficor :, labs at elevations 25 ft. and 0 ft. The Containment Sitell and Internala are connected to the foundation mat which is founded on rock. The working floor slab at the bottom of the containment is at El. (-) 26'.
The s tructural stec i frame involved in this detinn deficiency u., the annular steel frame located inside the contatnment building in tne annular space between the containment secondary shield wall and the contait= cat cuter shell.
The annular steel frame consists of steel columns and platf.:rm f ra :-
ings at elevations 25 ft. and 0 ft. It also has framings at various ic, ;e r clevations which are essentially utilized for pipe supports. Severai radial beams of the annular steel framing are rigidly connected to the F
containment secondary shield wall.
Desien Deficiencv
~
In late September 1979, a UE&C employee assigned to perform the seismic response analysis of Safety Class 2 and 3 piping in the containment building (including piping running in the annulus, supported by the structural steci framing) was reviewing tiic file of Scabrook Amplified Response Spectra (.\RS) for the proper input to his particular analysis. lie came upon the document se 1
P
,W * -
i 3.-
Design De fici ency. (Cont 'd) i entitled "Sei.smic Analysis of the Annular *; teel", with toe unique Menti-fication nu:uber SCSAC-14CS, dated October 7, l977. in reviewing the
' contents of this document,*the analyst determined that certain af the A s for portions of the annular structural steci in that document had consid-erably higher "g" values that those used as input to previous analyses of Safety Class 2 and 3 piping supported by the saue annular structural steel.
Further investigation revealed that the seismic analyscs of Safety ,
Class 2 and 3 lines in the same area performed to that time used as input ARS extracted from a document, entitled "Scismi.e Analysis of Containment Structure", with the unique identification number S3 SAC-4CS4, dated 3/19/76.
This document presented the ARS for the reinforced s ancrete contair ent outer shell and the interior concrete structures including the secem!aq.
shield walls. The ARS values contained in this c.;ocument arc, in p neral, lower than the previously mentioned document since, by their nature, concrete structures in general are stiffer than structural steel structures.
fhe immediate design deficiency was, therefore, thac Safety Class 2 and 1 piping systems were scismically analyzed using incorrect, low values of ARS. The possibility exists, therefore, that had this deficiency not -
been revealed, one or more of the piping systems in question would be over-stressed under maximum scismic and operating loadings.
Corrective Action
- l. UESC is conducting a short-term audit of selected setumic Category I systems and components to assure use of correct A::plified Response 2,
Spectra in their scismic design. ..
t
-e -
s 4-Corrective Action (Cont'd)
- 2. Containment building annular .tect f ra:ue ia being redeaig.ed to increase its rigidity. The intent is to reduce the valuca of the ARS imposed on the piping systems and other componentu supported by the annular steci frame.
- 3. A "110LD" has been placed on the design and analysis of piping systems located in the containment annulus.
- 4. UE&C will conduct a longer term audit of all seismic Category I systems and components to assure use of currect ARS in their seismic destga.
- 5. When the redesign of the annular s teel f raming is comple te , a scismic analysis of it will be performed, generating ntw .iRd at significant individual points.
- 6. Existing analyses of Safety Class 2 and 3 pipint, running in the containment annulus will be reviewed against ARS generated in 5
- 5 above. Where necessary, piping will be reanalyaed to assure conformance with applicable Code and regulatory requirements.
~
- 7. UE&C is currently reviewing the seismic design requirements of all other components supported by the containment annular steel frame. They are the followtug:
- a. Containment Recirculating Air Units : ,
These would be used for post-LOCA hydrogen mi::ing and are Safety Class 3.
,s *
t A
=
y
_ _ _ . _ ___. _. . . _ . . . _ . _ . . _ _ _ _ _. ..-_m.. _
-3 T.
1, .
Corrective Action (Cont'd)
- b. Containment Cooling Units:
Thrse are non-sdfety-related, non-sciumic Category *.. !!uwe v t. r ,
they util be seismically designed since they are located in a seismic Category I building,
- c. Hydrogen Recombiners:
There are two thermal-type recombinces mounted on the annular secci frame. They are safety Class 3, seismic Category I.
- d. Cable Trays and hcir Support Systems:
Tray supports are scismic Category I.
- e. Heating, Ventilating and Air Conditioning Ductworx. Syste.ui:
These are a mixture of Category I and non-Categorj I qutem: . .
- f. Air Compressors:
Two small non-Category I units for inutrumentation anl control supply.
- 8. Existing UE&C procedures involving scismic deui.gn, especially those treating Amplified Response Spectra, are under review to determine the need for revisions or additions which will upgrade them in areas of selection, use and review o f ARS.
- 9. Quality Assurance training sessions, in addition to thoue the regular schedule, are planned on the subject of ARS t rea ta:e n t for all UE&C personnel who interface with ARS.
s.
. , _ , _ . _ - - ._ '~.T' ~ ' ' '
. 6-i
~
Construction Stntus
'the Seab rook cont ainment buildity,, linit 1. structor.il m.i t anti till mat have been poured. Ibe cylindrical shell liner plate h.is bu s, erected to El. 119'-0". Internal concrete, including primary and seconuary shield walls, are in various degrecs of forming, reinforcing bar installation and concrete pouring to approximately Clevation O'.
The contain: cent annular steel has not beca released for fabrication.
It is anticipated that the aforementioned annular steel redesign work and its scismic ar.alysis will be complete in a timely manner so that the prefab-ricated stccl can be d111vered and crected in accordance zith the prt.sent cons truction schedule - July 1980.
The piping systems analyced using incorrect .\RS have been releawd ;.cr fabrication. Engineering experience and judgement predict that en reanalysis, the geometry and wall thicknesses of these systems util not changu, peta ps only the nu:rber and location of seismic supports. In any case, v.cca.e t ry o f prefabricated piping could be modified in the Cicid. Pipe and other ccmpunent crection in the containment annulus is scheduled o con:nence approximate 1.
July 1,1980, and to continue for a period of about tuo years.
Final Reoort The final report on this subject, including a discussion of any safety implications, and the results of the corrective actions enumerated above, will be complete and issued by June 1, 1980.
.\,
t
/ .
,. D f. ConstnsCtor c irc noe,?C'e L C-r;o'd 30 Soutn 17th Stre t . ..;, . . u c Post Office uox 8r3 %^ : Mm
- Philadelphia, PA 19101 VIA TELECOPIER
!iovember 6, 1979 .
SP.U-31426 file: 3.1.6 Catg: : ICD
!!o Response Required tir. John DeVincenti s , Project Manager Yankee Atomic Electric Company Scabrook Station 20 Turnpike Road Westborough, Massachusetts 01581 .
Dear Mr. DeVincentis:
Public Service Company of !!cw Hampshire Scabrook Station Discrepancy in the Seismic Design in the Containment Annular Area he purpose of thi s 1ctter is to advise you o f a des t;,n discrepanc ,
in the anplified response spectra used in the scismic desir,n of na:ety
. related components supported by the containment annular steel frame.
It was recently discovered that the analyscs being donc for campo-ncnts supported by the containment annular steel f rame were based on incorrect scismic amplified response spectra. He a:r. ell fied response spectra used for this design was that for the contain.:ent interior con-crete and not the annular steel frame which should have been used.
An evaluation has shown that the amplified response spectra for the annular steel frame has "g" values greater than that used in the compo- ,
nent design. Some o f the peak values are such that it is unlikely a satisfactory component design could be achieved.
Action is currently undervay to redesign the containment annular stee'. frame by providing additional bracing in order to reduce the ";"
values. We desien of all components located in this area will then be checked against the redesigned containment annular steel frame and its resulting amplified response spectra.
The containment steel annular f rame has no yet been released for fabrication and will be held until the additional bracine in desi . ned, ne manufacture of a number of components in this area has been released, but it is not intended to place a hold on these items since it in believed that a satis factory design can be achicved without significant .
changes to the components.
A
- .S T r.<. . l A Revtbean Company
... - . . . . . . - . . .- - - - _ . ~ .5 s
if r . Jchn DeVincentis ;;a./cu:> c r 6, 1979 Project Manager S3U-31426 In order to ensure that other discrepancies do not e:< i s t in tae seismic design, an audit will be performed to ensure that the preper ampli fied response spectra was used in the dest;n of all ite=s on the Scabrook project.
We will keep you advised of our progress in resolving this problen and completing the audit of the other items. -
It is our belief that this design discrepancy is a reportable . t e:::
in accordance with 10 CTR 50.55(c) and it is, t h e r e :~o re , r e c e:=e nd e. '
that it be reported to the fiuclear Regulatory Cent.ission.
Very truly yours,
/A <
ji (.c'k G. F. Cole Project :anager GFC:hr cc: Messrs. John DeVincentis - YAEC - 4L B. B. Beckley - PS;al - 3L J. D. Haseltine - PStal - 1L T. ft. Sherry - YAEC - 1L J.11. Iterrin - PS!al - YAEC Field Of fice - IL O 2
=e--.e_m...-- - - . -