Similar Documents at Surry |
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Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18151A2861998-01-26026 January 1998 SPS Unit 2 ISI Summary Rept for 1997 Refueling Outage ML18151A3111997-07-21021 July 1997 Inservice Inspections Abstract of Exams. ML18151A4381996-08-0808 August 1996 Form NIS-1 Owner Rept for ISI, Required by Provisions of ASME Code ML18152A1901995-12-31031 December 1995 Vepc SPS Units 1 & 2 1995 Annual SG ISI Rept. ML18151A2811995-12-27027 December 1995 Form NIS-1 Owner Rept for Inservice Insps, as Required by Provisions of ASME Code Rules ML18151A2281995-06-0707 June 1995 NIS-1 ISI Summary Rept for June 1995. ML18151A2241994-05-24024 May 1994 ISI Summary Rept for 1994 Refueling Outage ML18153A8731994-02-23023 February 1994 Annual Steam Generator ISI Rept. ML18151A2781993-11-10010 November 1993 IST Program Plan for Pumps & Valves Third Insp Interval 940510-20051, Rev 0 ML18151A2221993-05-0606 May 1993 Refueling Outage 2nd Interval,3rd Period Isi. ML18153D2381993-02-0909 February 1993 Annual SG Inservice Insp Rept. ML18151A2051992-07-15015 July 1992 ISI Rept for Surry Power Station Unit 1 for 1992 Refueling Outage,2nd Interval,3rd Period. ML20094H0271991-12-31031 December 1991 1991 Annual Steam Generator Inservice Insp Rept ML18151A1591991-09-0505 September 1991 Inservice Insp Rept of Surry Nuclear Power Station Unit 2, Second Interval,Second/Third Period. ML18151A1561991-03-12012 March 1991 Inservice Insp Summary Rept for 1990 Refueling Outage. W/910312 Ltr ML18153C5481991-02-25025 February 1991 Annual Steam Generator Inservice Insp Rept. ML18153C1391990-03-0808 March 1990 Suppl to Inservice Insp Rept,Consisting of NIS-2 Forms for Stud & Nut Replacement ML20011D3861989-11-27027 November 1989 Inservice Insp Rept of Surry Nuclear Power Station Unit 2, 2nd Interval,2nd Period. ML18153B6251989-03-0101 March 1989 1988 Annual Steam Generator Inservice Insp Rept. ML18151A2531988-10-10010 October 1988 Inservice Insp Summary Rept of Surry Power Station. ML18130A4441987-04-0101 April 1987 Rev 1 to Surry Power Station Unit 2 Inservice Insp Program, Interval 2,830501-930501. ML20205J9641987-03-30030 March 1987 Suppl to Owners Rept for Inservice Insps & Exams, Conducted on 850625-861202.Exam Resulted in Total of One Nozzle Weld Being Reported on Basis of Procedure Recording Criteria ML18130A4401987-03-27027 March 1987 Rev 3 to Surry Power Station Unit 1 Inservice Insp Program, Interval 2,821222-921222. ML18150A5201986-12-31031 December 1986 1986 Annual Steam Generator Inservice Insp Rept,Eddy Current Exam. ML20205F5081986-11-14014 November 1986 Inservice Insp Rept of Surry Nuclear Power Station,Unit 1 ML18139B5571981-08-31031 August 1981 Inservice Insp Rept on 800920-810705.Exam Procedures Were Approved Prior to Exams & Certification Documents Re Personnel,Equipment & Matls Were Reviewed & Determined to Be Satisfactory ML18139B5551981-07-31031 July 1981 Inservice Insp Rept on 810301-0705.Exams Conducted to Review Exam Zone within Geometric,Metallurgical & Physical Limitations.No Indications Found to Be Recordable ML20087B7671975-11-25025 November 1975 Inservice Insp Program,Refueling Outage 2. Insp Verified Integrity of Sys & Components ML20086Q1781975-06-15015 June 1975 Preliminary Results of Inservice Insp Program,Refueling Outage 1. No Significant Deficiencies Identified 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 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. ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un. ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket 1999-09-30
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- PRESERVICE INSPECTION REPORT of the ~, SURRY UNIT NO. 1 NUCLEAR POWER STATION P.O. BOX 315 j SURRY, VIRGINIA 23883 For Virginia Electric and Power Company P.O. Box 26666 Richmond, Virginia 23261 REPORT DATE: JULY 1981 COMMERCIAL SERVICE DATE: DECEMBER 22,1972 OPERATING CAPACITY:
822 MWE 1 8110060241 811002 " PDR ADOCK 05000280 G PDR Performed By: Virginia Electric and Power Company Surry Power Station NDT Department P.O. Box 315 Surry, Va. 23883 FORM NIS*l (back) I. Examination Dates 3/ 1/ 81 to 7/5/BL 9. Inspection Interval from 12/22/72 to -12/22/82
- 10. Abstract or F.xaminations.
Include a list of examinations and a statement concerning starus_ of '!"ork required for curTCnt interval.
Ref ere nee Tab C ~, *~ II. Abiuact or Conditions Noted Reference Tab B -:::-* 12. Abltract of Corrective Measures Recommended*and Taken Ref ere nee Tab *e We certify that the statements m::ade in this rcpon arc correct and the examinations and corrective mca-: uk; ~";~; rul~:;; AS:::" S<<U:;:~ ~y~j__ . Owner ENG EERifG SUPERVISOR OF N. D. T. Certificate of Au:horization No. (if applicable)
$ Expiration Date J"i)fr . CERTIFICATE OF INSERVICE INSPECTION
- -I. the undersigned, holding a valid commission issued by the National Board ofi Boiler id PJ"essurc Vessel
- 1 Tr,~ Heu*f "r,:,Sty,,r,-
~/r, Inspectors and/or the State or Provmce o , "fr, fJ, cv and employed by~ 7::dl( f:'.-Z:NS r'o 'Qf H;;,1/i~/
cy,,,n, have in~ted the com; ~ents described in this Owners* Data Rcpon during the period , to 7~/ f I . and state that to the best of my knowicdgc and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Repon in accordance with the requirements of the ASME Code,Section XI. By signing rhis certificate neither the Inspector nor his employer makes any warranty.
expressed or implied, concerning the examinations and corrective m~asures described in this Owners' Data Repon. Furthermore, ncidaer the Inspector nor his employer shall be liable in any manner for ariy personal injury or property damage or a loss of any kind arising from or connected with this inspection.
I J:oitM NIS-1 OWNEl{S' DATA REl'OHT FOR INSER\'ICE INSPECTIONS As required hy chc Provi,;ioru of the ASME Clldc ll\llcs 1. Owner Virginia Electric And Power Co11_1.Q..any P.0-. Box 26666,Richmond,VA.___21261 (Name and Address of Owner) 2, rlant Surry # l , P
- Box 31 5 '* S l!_r...!:.Y..i Vi rg,..:.i _n "'-'; a::.__::2:...:::;3~8..::..83.;;._..
__ _..;... __________
_ (N:une and Address of Plant) ,,,._ J. Plant Unit __ 1 ______ 4. Owner Certificate of Authoriz;!tion (if rcquirc;d)
__ N:..../ A ____ _ ~':-5. Commercial Service Date l 2 /22/72 6. National Bl,ard Number for Unit __ __..N~/._.A'""--------7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Install er Serial No. Province No. Boaid ?"-.Ju. Reactor Vessel Rotterdam RCPCRV 137-1 ------R. V. RCRIUI Internals Allis-Chalmers RCRILI ------Pressurizer Westinghouse RCPCPR ---1031 St. Gen. 1 Westinghouse 2981 ---681 St. Gen. 2 Westinghouse 2982 ---682 St. Gen. 3 Westinghouse 2983 ---683 Reactor Coolan Piping Southwest Fab. CQ. ---------Class l Piping Southwest Fab. CQ. ---------vl ass 2 Piping Southwest Fab. Co. ---------R.C. Pump 1 Westinghouse 458 ------R.C. Pumo 2 Westinahouse 459 ------R.C. Pumo 3 Westinahouse 460 ------Valve 1-595 Darling ---------Valve 1-700 Copes Vulcan ---------I V.a 1 ve 1-8750 Darl ina ---j -------RJ.IR HX l A Atlas Industrial 890 ---740 , Note: Supp!cmcmal sheets in form of lisrs, sketches, rJr drawi111:s may l,c used provided ( 1) si:r.c is 8'1, i11. x 11 in., (2) informarion in irl*rns 1 rhrou,:h 6 on this .:fata reporr is .inl'ludcd ,m Cal*h sheet, anJ ( 3) eu*h shcct is numbered and the number of shc.-crs i,; n*l*orJL*J
.11 rhc "'f' of rhis form. This form ([00029) may he c,t.,1c1i11cd frvn, thu Ordor D<<?Pt., ASME, 345 E. 47th St., Now Ycwk, N. Y. 10017 '
- FORM NIS*l OWNERS' DATA REPORT FOR JNSERVICE INSPECTIONS As required by the Provi~ions of the ASM[ Code Rules 1. Owner Virginia Electric And Power Company P.O. Box 26666.Richmond.VA.
23261 (Name and Address of Owner) 2. Plant Surry Ill, P.O~Box 315,Surry,Virginia 23883 (N:ame and Addrci.s of Plant) :.:: !J. Plant Unit __ l ______ 4. Owner Certificate of Authorization (if required)
__ N_/_A ____ _ _ -_*s. Commercial Service Date 12/22/72 6. National Board Number for Unit __ ___.N~/c...oA..._
_____ _ 7. Components Inspected
'
- Manufacturer I Component or Manufactur~r or Installer State or Nationai Appurtenance or Installer . Serial No. Province No . Board No. RHR HX lB Atlas Industrial 891 ---741 seal Water Heat Exch. Joseph Oats & Sons 1817-2A ---346 Regenerative 4195-A3-7 369 HX Sentrv 4195-A3-8
---370 4195-A3-9 371 Volume Control Tank Richmond Eng. L-8554 ---57783 Lnargrng Pump lA Byron Jackson Pumps ---------. I -\ . a -Note: Supp!emC'ntal sheers in form of lists. skc:tdaes, or drawinr,s may be used provided ( J) size is 8~ in. x *1 t in., (2) inform.:nion in items 1 rhrou 6 h 6 on this .fara rC'port i~ included ,,n eai:h sheer, anJ ( 3) each sheet is numocred and the number of shC'cts i~ recorded at rhe top of rhi:-form. This form (E00029) may oo obtdinod fr.:irr, thu Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017 A summary of the indications is as follows: Fro~_all inspections performed for the preservice examination of Unit one no Q1dications were found to be recordable.
Examinations Examinations were conducted to review as much of the examination zone as was practical, within geometric, metallurgical and physical limitations.
When the required examination volume or area could not be examined 100%, the examination was considered to be partial (PAR) and so noted. Generally, PAR's are noted at fitting-to-fitting assemblies (as explained under LIMITATIONS) and in areas where integrally welded supports, lugs, hangers, etc., preclude accesi to some part of the examination area. Ultrasonic examinations that produced greater than reference level sensitivity from reflectors that are characteristic of metallurgical structure of the I.D./0.D.
surfaces of an item were acknowledged for information only and were noted as such on that data sheets. Examples of areas that generally produce such geometric indications include: (1) I.D. weld prep or root and or the crown overlay or toe. (2) The I.D. radius of the tube sheet on the channel head to tube sheet weld of steam generators, when examining from the tubesheet side. (3) The metallurgical structure of cast materials.
(4) Responses from the thread areas of bo 1 t i_ng. Geometric responses from these areas are charateristic*of the examination and are not considered relevant for reporting le_ngth or depth. Limitations Some of the arrangements and details of the p1p1ng system and components were designed and fabricated before the access and examination requirements of Section XI of the 1974 Code could be applied; consequently some examinations are limited or not practical due to geometric configuration or accessibility.
Generally these limitations exist at all fitting to fitting joints such as .e1bow to tee,. elbow to valve,-reducer to valve, etc. where geometry and tim~ surface condition preclude ultrasonic coupling or access for the required scan:length.
The limitations exist to a lesser degree at pipe fitting assemblies, particularly where the weld is not ground flush with the pipe O.D. surface. At these joints examinations can be conducted from the pipe side, however, the fitting again limits or pr~cludes examination from the opposite side. When the weld surface is flat, the fitting side examination is replaced by a calibrated straight beam examination on the weld. .,i ,,
- In most cases, examinations in these areas were accomplished as a best effort attempt to cover as much of the code required area or volume (generally, the weld and base metal for 1 11 T 11 on each side) as is possible, however, the extent of examination coverage in the base metal of the fitting or component cannot be spe~ifically qualified.
_ :,;~-""Areas where complete examination of 100% of the required .volume or~*area could not*:be achieved are indicated by a PAR (partial) notation on the examiner's dat-~-sheet, and the 1 imiting cause is noted. The principal basis for PAR 1 s is to identify the inability to examine 100% of the required base metal volume for the 1 11 T 11 distance beyond the edge of the weld on a fitting or component, such as: ultrasonic examination of* a pipe to elbow assembly, where scanning on the intrados of the elbow causes de-coupling of the sound beam; or a pipe to flange or valve assembly, where scanning the entire volume on the fitting or component side is limited by con f i gu ration. The resultJng coverage is such that examination of the weld, heat affected zone and base metal for 1 11 T 11 on the pipe side can be achieved by scanning from the pipe side of the weld. An indeterminate coverage of the base metal on the fitting or component side may be achieved during this pipe side scan depending on the calibrated sweep length, attenuation, joint configuration, etc.; however, the volume on the fitting or component side additionally cannot be scanned completely for transverse indications as required by Code. In either case, 100% of this 1 11 T 11 volume cannot be assured, thus a PAR is required as a disclaimer to having satisfied code requirements, albeit the intent is satisfied to the extent practical.
Specific limitations and restrictions for all examinations are as indicated on the raw data sheets .