|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18066A2771998-08-13013 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 ML20141C4931997-06-17017 June 1997 Part 21 Rept Re Nonconforming Raw Water Pump Impellers.Raw Water Pump Assembly AC-10D Replaced Due to Normal Wear on Pump Internals,Namely Pump Impellers & Impeller Liners ML20148D1201997-05-23023 May 1997 Part 21 Rept Re Replacement Impellers for Byron Jackson Raw Water Pumps Having Blade Dimensions Out of Tolerance Due to Normal Wear on Pump Internals.Replaced Raw Water Pump Assembly AC-10D LIC-94-0164, Part 21 Rept Re Nonconformance in Potentiometers W/ Attachable Switches Mfg by Ohmite & Supplied by Abb C-E. Nonconforming Components Returned to Abb C-E & Abb C-E Issued Info Bulletin 94-02,providing Appropriate Guidance1994-08-24024 August 1994 Part 21 Rept Re Nonconformance in Potentiometers W/ Attachable Switches Mfg by Ohmite & Supplied by Abb C-E. Nonconforming Components Returned to Abb C-E & Abb C-E Issued Info Bulletin 94-02,providing Appropriate Guidance ML20071J5271994-07-26026 July 1994 Part 21 Rept Re Ohmite Model CU1021 & CU1031 Potentiometers Model CS-1 Switches Supplied by Abb C-E.Verified That Potentiometers/Switches Combinations Not Installed at FCS in Location Which Could Have Adverse Safety Implication ML18096B2421993-02-0101 February 1993 Part 21 Rept Re Possible Matl Defect in Stainless Steel Swagelock Tube Fittings.Initially Reported on 921218.List of Part Numbers,Heat Codes & Addl Affected Customers Encl ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl 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 ML20085D4971991-10-0707 October 1991 Part 21 Rept Re Cracking in Casing of Exide Type GC-23 Batteries Produced Prior to 1983.Initially Reported on 911003.Caused by Inadequate Design of Cell Terminal Post Seals.Use of pre-1983 Subj Batteries Discontinued ML20079H0921991-08-27027 August 1991 Part 21 Rept Re Failure of Roll Pin Mfg by Cardinal Industrial Products,Corp & Used on DG Damper Actuator Due to Phosphorus Segregation Caused by Improper Tempering Heat Treatment.Inlet & Outlet Dampers on DGs Opened ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20141C9361986-03-17017 March 1986 Part 21 Rept Re Containment Spray Sys Recirculation Lines. Initially Reported on 860311.Matter Under Investigation to Determine Remedial Course of Action.Staff Will Be Kept Informed of Progress ML20199F3351986-03-17017 March 1986 Part 21 & Deficiency Rept Re Failure of Disc Guide Assembly Springs in HCV-247 & HCV-248.Initially Reported on 860314. Springs Replaced & Valves Tested Quarterly.Other Utils Contacted Via Nuclear Network Sys ML20064J5801982-11-0808 November 1982 Part 21 Rept Re Matl That May Not Be in Compliance W/ 10CFR50,App B,Section Viii Requirements.Matl Supplied to Ne Public Power District & Omaha Public Power District.Qa Depts Contacted Re Resolution of Nonconformance Situation ML20010B6741981-07-31031 July 1981 Deficiency Rept Re Potential Defect W/Tornado Venting Sys. Inhouse Assessment Will Be Completed by 810910.Also Reported Per Part 21 1998-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 LIC-98-0136, Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With ML20155G4261998-09-30030 September 1998 Performance Indicators for Sept 1998 ML20154A1251998-08-31031 August 1998 Performance Indicators, Rept for Aug 1998 LIC-98-0122, Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With ML20238F7231998-08-17017 August 1998 Owner'S Rept for Isis 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 1999-09-30
[Table view] |
Text
i A-Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536 4000 March 17, 1986 r TS-FC-86-165 h,?i @ Lgp 1:'a c p' . t LIC-86-094 1
! MAR I 91986 l i
Mr. R. D. Martin b ' ' ~~~ ~- ~
Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
Reference:
Docket No. 50-285
Dear Mr. Martin:
10 CFR 21 Report on Failure of Disc Guide Assembly Springs in HCV-247 and HCV-248 Omaha Public Power District, holder of Operating License DPR-40, has investi-gated and found the recent failure of the disc guide assembly springs in HCV-247 and HCV-248 to be 10 CFR 21 reportable. OPPD notified Mr. Doyle Hunnicutt of the Region IV office on March 14, 1986, of the attached information. The attached report provides the necessary details of this event as required by 10 CFR 21.
Sincerely, 24 R. L. Andrews b
Division Manager Nuclear Production RLA/rh 8603280163 860317 Attachment P79 ADOCK 05000205 G PDR cc: Mr. James M. Taylor, Director Office of Inspection and Enforcement (3)
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, DC 20036 Mr. E. G. Tourigny, NRC Project Manager Mr. P. H. Harrell, NRC Senior Resident Inspection C) p~ '
..s _
, _ = = _ , t
l y
i 10CFR21 REPORT ON FAILURE OF DISC GUIDE ASSEMBLY SPRINGS IN HCV-247 and HCV-248 INTRODUCTION During the 1985 refueling outage valve failures were discovered in HCV-247 and HCV-248. These valves are 2 inch Series V526 Valcor solenoid operated globe valves (Model V526-6190-4, P/N 454660001). HCV-247 and HCV-248 were. installed in December of 1982 as redundant valves, per the requirements of 10CFR50, Appen-dix A, Sect IV, Criterion 35, for the long term core cooling system. HCV-248, in series with HCV-239, provides a flow path from the charging pumps to loop 2A. HCV-247,. in series with HCV-238, provides a flow path from the _ charging pumps to loop 2B (Ref. P&ID E-23866-210-120 Sh. 1 of 2). These valves were purchased from Valcor Engineering Corporation, 2 Lawrence Road, Springfield, New Jersey 07081 ((201) 487-8400).
Problems with HCV-247 and HCV-248 were first experienced in August 1985 during equipment rotation. The valves closed during this equipment rotation and could not be reopened without securing all charging pumps. Increased valve stroke times were also noted. Discussions with Valcor Engineering Corporation deter-mined that the problem was most likely to be the main disc bleed hole in the valve. Plant Staff concluded that continued operation with the existing valve p'roblems would not be adverse to plant safety (FC-1243-85) and, therefore, operation was continued until the end of the fuel cycle.
During the subsequent refueling outage the valves were disassembled and exam-ined to determine the cause of the valve malfunction. It was found that failure of both disc guide assembly springs (P/N V52604-6190-4 and V52615-6190-4) in both valves had resulted in the valve malfunctions. The failure of the spring was complete and catastrophic, in that nearly all of the spring coils had failed. Most remaining pieces were only 1-2 coils in length compared to an 1
initial length of 25 coils. Construction of the valves is such that the spring remnants were retained in the valve internals.
EVALUATION Discussions with the Valcor representative revealed that this was not the first time that Valcor had experienced such a valve failure. A similar malfunction had occurred at' Prairie Island Nuclear Generating Plant on the Containment Hot leg Sample Line. Examination of the failed spring at Prairie Island was conduct-ed by Fairfield Testing /Labtech, Inc.. This testing found that this failure was due to hydrogen embrittlement (Lab Reports S1588 and-S1531). OPPD submitted the failed valve springs from HCV-247 and HCV-248 to Orr Metallurgical Services for examination. It was their opinion that the failure of these springs was also the result of hydrogen embrittlement (02/26/86 letter from Orr Metallurgical).
Such a common mode of failure at more than one nuclear generating station would.
seem to imply that this problem may well be experienced by any Valcor valve us-ing precipitation hardened stainless steels for internal components which may be exposed to primary coolant conditions.
i
- t. . -
l I
The failure of these two. valves has th'e potential to render both of.the normal charging paths to the reactor coolant system inoperative. Such 3
failure would result in loss of charging 'or makeup until alternate charg-3 ing paths were established. Alternate charging paths are available through
- the pressurizer spray line and the safety injection system. Charging paths i as required by Technical Specifications Sect. 2.2 part 2d. would still be j available, however, it -is likely that in case of a total' failure, reactor 3
shutdown would be required to resolve the problem.
i' 4
At the time HCV-247 and HCV-248 were purchased, two other valves, HCV-2988 and HCV-249 were also purchased and installed as part of the modification i
to provide redundancy for long term core cooling. These valves are also'
, Valcor V526 Solenoid operated globe valves. HCV-249 is .in parallel with l HCV-240 and provides a flow path from the charging system to the auxiliary -
1 pressurizer spray line. HCV-2988 is in parallel with HCV-308 and provides
- a cross-tie between the safety injection system and the charging system.
Inspection of the internals of these valves was conducted after the fail-ure of HCV-247 and HCV-248 disc guide assembly springs was' discovered..The .
springs in these valves were found to be in good condition. It is believed
, that this is due to the fact that these valves are normally closed and are l on dead legs of piping in the chemical and volume control system (Ref.
P&ID E-23866-210_-120 Sht.1 of 2 and E-23866-210-130 Sht.1 of 2). It is
! also believed that the lower temperature conditions at these valve loca-
- tions are less conducive to accelerated hydrogen embrittlement.
1 i
Other Valcor valves are also used at Fort Calhoun Station. None of these, however, are installed in primary systems where the potential for hydrogen :
embrittlement exists. HCV-921 and HCV-922 are isolation valves for the main steam radiation monitor. HCV-820A, HCV-821A, HCV-883A, HCV-8848, HCV-8208, and HCV-8218 are all valves which allow sampling of. the contain-ment air system for hydrogen. There is no reason to believe that these j valves are subject to a similar malfunction.
i HCV-247 and HCV-248 were repaired by replacing the disc guide assembly
! springs and re-assembling the valves. The replacement' springs were also
- constructed of 17-4PH stainless steel because springs made of inconel
- could not be obtained in time to meet the reactor startup date. This i inspection and repair of HCV-247 and HCV-248 was completed on November 18,
- 1985. It is expected that, based on previous experience,-the replacement ;
} springs will function properly for approximately 18 months, which is well i
beyond the next refueling outage. Additionally, valves are tested quar-j terly to ensure that they cycle properly. EEAR FC-85-179 has been reis- '
l sued to replace HCV-247, HCV-248, HCV-249, and HCV-2988 during the next '
j refueling outage scheduled for March of 1987.
I l CONCLUSIONS 1
i It is recommended by this utility that all plants having Valcor valves.in primary systems examine their records for this ' defect. It would appear 1 that this problem would be primarily limited to PWR's as they utilize
! excess dissolved hydrogen for chemistry control.
l' Valcor Engineering has indicated to OPPD that it has now replaced the stainless steel springs with springs constructed of inconel for all valves used in such applications. Valcor has also stated that they have informed all utilities owning such valves of the potential for failure of these
- _ stainless steel springs.
..\.
~
It is anticipated that this report will aid other utilities in identifica'-
1 tion and correction of this potential problem. OPPD has sent a notice to other utilities via the Nuclear Network System to inform them of this pro-blem and encourages other utilities to contact us for more information -if necessary.
4 i
)
i I
i l
i d
-- . . - . - . . - . - . . . -. . .__. . - _ . ...