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Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20203K9821998-02-26026 February 1998 Results of Bobbin Coil & Motorized Rotating Plus Point Exams for Unit 2 SG Numbers 21 & 22 ML20210M6711997-08-19019 August 1997 ISI Summary Rept for Calvert Cliffs Unit 2 ML20129D6801996-09-30030 September 1996 Final Rept Spring 1996 Inservice Exam of Selected Class 1 & 2 Components at Calvert Cliffs Nuclear Power Plant,Unit 1 ML20135A5881996-04-30030 April 1996 SG 12 Final Repts ML20135A5841996-04-30030 April 1996 SG 11 Final Repts ML20078S4261995-02-17017 February 1995 SG 11 & 12 Eddy Current Insp Final Rept Mar 1994 ML20072D2591994-08-11011 August 1994 ISI Rept for Calvert Cliffs Unit 1 ML20072D4501994-07-31031 July 1994 Spring 1994 Inservice Exam of Selected Class 1,2 & 3 Components at Calvert Cliffs Nuclear Power Plant,Unit 1, Final Rept ML20058F1971993-11-30030 November 1993 Supplemental Forms NIS-2 on Repairs or Replacements to ISI Rept for Calvert Cliffs Unit 2 ML20029B3951991-02-28028 February 1991 Steam Generators 11 & 12 Eddy Current Testing,Final Rept May/June 1990. ML20029B3961991-02-28028 February 1991 Steam Generators 21 & 22 Eddy Current Testing,Final Rept Aug/Oct 1990. ML20154S7591988-08-31031 August 1988 Vols IV & V to, 1988 Inservice Exam of Selected Class 1, Class 2 & Class 3 Components & Sys of Calvert Cliffs Nuclear Power Plant,Unit 1, Consisting of Field Data ML20236K9741987-07-30030 July 1987 Generators 21 & 22 Category C-3 Rept Re Inservice Insp During Mar/Apr 1987. Indications Found in 177 of 8,497 Tubes Examined in Steam Generator 21 & 126 of 8,511 Tubes in Steam Generator 22 ML20237J6611987-06-0909 June 1987 Inservice Insp Rept for 850828-870112,per ASME Boiler & Pressure Vessel Code Section Xi,Form NIS-1 ML20237J6251986-06-0909 June 1986 Inservice Insp Rept for 840701-851207.Listed Components or Appurtenance Inspected for Conformance W/Asme Boiler & Pressure Vessel Code Section XI ML20102B8541984-11-26026 November 1984 Inservice Insp Rept for 830118-840701,describing Eddy Current Exam of Steam Generators 1999-07-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs LD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced ML20151Y1191998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237B9371998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant ML20237D5941998-07-22022 July 1998 Rev 2 to Ccnpp COLR for Unit 2,Cycle 12 ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20236R0881998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20236X3101998-06-19019 June 1998 Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12 ML20249A9571998-06-15015 June 1998 Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc ML20249A7711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2 1999-09-30
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- ENCLOSURE (1)
To BALTIMORE GAS AND ELECTRIC COMPANY'S INSERVICE INSPECTION REPORT FOR CALVERT CLIFFS UNIT 2 ;
ASME BOILER AND PRESSURE VESSEL CODE SECTION XI, FORM NIS-1 n.
8708260241 860924 PDR ADOCK 05000317 G PDR
l ," . DATE: June 9,1986 NIS-1 PAGE 1 of 4 FORM NIS-1 FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) 1.. Owner: Baltimore Gas and Electric Company P.O. Box 1475 Baltimore, MD 21203
- 2. Plant: Calvert Cliff s Nuclear Power Plant Lusby Post Office Lusby, MD 20657
- 3. Plant Unit: h2 4. Owner Certification of Authorization: NA
- 5. Commercial Service Date: 6. National Board Number for Unit:
April 1,1977 20912
- 7. . Components inspected:
COMPONENT MANUFACTURER MANUFACTURER STATE NATIONAL OR 'OR OR INSTALLER OR BOARD APPURTENANCE INSTALLER SERIAL # PROVINCE # NUMBER Reactor Combustion CE-67108 14001NY 20912 Pressure / Engineering Vessel Reacto- Combustion CE-67208 14001NV 20912 Pressure Engineering Vessel Closure Head Steam Combustion CE-67306 14001NV 20925 Generator Engineering
- 21 Steam Combustion CE-67307 14001NV 20924 Generator Engineering
- 22 i Reactor Combustion Contract No. '
Coolant Engineering 72467 Pipe-Drain Lines Bechtel f/21 A Reactor Byron Jackson SN-0441 63-1-N-0-441 Coolant Pump ~
j
- 21B Reactor Byran Jackson SN-0442 68-1-N-0442 ;
Coolant Pump
- 22A Reactor Byron Jackson SN-0443 68-1-N-0 443 l Coolant Pump l
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- t i f f *- DATE: June 9,1936 .
NIS-1 fj AG . *2 of 4 FORM NIS-1 I
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- 7. Comporw;nt.c Inspected: . (Cor.i.inued) t i i q COMPONENT MANUFACI URER MANUFACTURER . STATE NATIONAL OR i OR 06.' INSTALLER ' OK -
. BOARD
, APPUR7siNANCE INSTALLER SERIAL # PROVINCE # NUMBER '
v228 Retetor Byron Jackson < SN-0*44 , 66-1-N-0444 Cooiant Twci >
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Saf e?.v - Bechtel '
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Piping /
Containment Bechtel '
Spray Piping .
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Shutdown ~T Bechtel Cooling Piping '
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g Main Steam ~"h Bechtel Piping Feedwater Sechtel Piping ,
, t ,i Pressurizer Bechtel >
- Spray Piping Charging bechtel Piping Pressurizer Bechtel
> 5afety & Relief i .
Regenerative Whiticck 73232 Heat Exchanger Spent Fuel Bechtel System High Pressure Blng5am Safety Injection Pump Low Presrure Indersoll-Rand Safety Injection Pump Containment Byron Jackson Spray Pumps
- 3. Examination Dates: July 1,1984 to December 7,1985
- 9. Inspection Interval: April 1,1977 to April 1,1987
_________a
[ DATE: June 9,1986 NIS-1 PAGE 3 of 4 FORM NIS-1
- 10. Abstact of Examinations: (include list of exams and statements concerning status of work requried for current intervai).
(See Enclosures 2 and 3).
The examinations reported herein constitute the sixth such inservice examination performed at Calvert Cliffs Unit 2, and the second within the third 40-month period of commerical operation. Calvert Cliffs Unit 2 examinations were performed in accordance with the 1974 Edition of Section XI with Addenda through Summer 1975. Hydrostatic and System Pressure Testing Procedures are available at the plant site for review.
I1. ' Abstract of Conditions Noted:
(See Enclosures 2 & 3)
- a. Eddy current examination of Steam Generators #21 and #22 revealed signs of steam generator tube degradation. Indications of degradation were found on a total of 59 tubes from the approximately 4,512 tubes examined (2,066 #21 .,
Steam Generator and 2,446 #22 Steam Generator). Thirteen tubes were found to have service induced degradation which exceeded the Technical Specification plugging limit of 40% loss of nominal wall thickness, nine in #21 Steam Generator and four in #22 Steam Generator. The indications were not localized in a particular area of the tube bundle.
- b. Corrosion was observed by Ultrasonic Testing and Visual Examination of #22A Reactor Coolant Pump Cover-to-Case Stud Numbers 1,2,3,8,9,10,13,14,and 15 and on #22B Reactor Coolant Pump Stud Numbers 1 through 4
_12. Abstract of Corrective Measures Recommended and Taken:
(See Enclosures 2 &3)
- a. Those tubes found to contain imperfections greater than 40% wall loss were removed from service by plugging each end with a mechanical tube plug.
- b. Reactor Coolant Pump stud number 9 was removed from service for further investigation. The indications were resolved as being caused by boric acid corrosion to the exposed threaded area of the studs. All RCP studs exposed surfaces were visually examined and cleaned. Visual examinations of the studs were performed at 0an elevated pressure of 2295 psia and a reactor coolant temperature of 500 F to insure that there was no further leakage of boric acid on the studs. Visual examinations will be scheduled during the next refueling outage for further evaluation or replacement.
We certify that the Statements made in this report are correct anc the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.
DATE: )"4 b ,19 b.
SIGNED: , Baltimore Gas & Electric Company A. R.T hornton General Supervisor - Plant & Project Engineering i-
! - - DATE: June 9,1986 NIS-1 1 PAGE 4 of 4 FORM NIS-1 Certificate of Authorization No. NA Expiration Date NA CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Bcard of Boiler and Pressure Vessel Inspectors and/or the State or Province of Maryland and employed by Arkwright-Boston Manufacturer's Mutual Insurance Company have inspected the components described in this Owner's Data Report during the period July 1,1984, to December 7,1985, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Data.
Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or impiled, concerning the examinations and corrective measures described in this Owner's Data Report. Furthermore, neither the Inspector nor his ernployer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
DATE: 8/M f ,19 4 c .
El INSPECTOR SIGNATURE '
44 ,e. e FACTORY MUTUAL SYSTEM COMMISSION: NB 82.2.6 ,Md (V7 National Board State Province and No.
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i' ENCLOSURE (2)
TO BALTIMCRE GAS AND ELECTRIC COMPANY'S INSERVICE INSPECTION REPORT FOR CALVERT CLIFFS UNIT 2 STEAM GENERATORS NO. 21 & 22 EDDY CURRENT EXAMINATION REPORT PREPARED BY ZETEC, INCORPORATED 6
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t ENCLOSURE (3)
To BALTIMORE GAS AND ELECTRIC COMPANY'S INSERVICE INSPECTION REPORT FOR CALVERT CLIFFS UNIT 2 SOUTHWEST RESEARCH INSTITUTE REPORT (VOLUMES I TO V) 4'
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