LER-1981-077, Forwards LER 81-077/01T-0.Detailed Event Analysis Encl |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3691981077R00 - NRC Website |
|
text
'
OFFiclAL COPY D UK E POWE R COSIPANY'. ;
Powru Ilt:st.ntxo age Sot: Tin Citt;ucts STneer, CitAut.oTTE, N. C. 2e242 8
]*
WILLI AM O. PA R M L A, J R.
7E L E PmO N E:AmfA 704
/tc6 PetSiOrNT src - e covce.o.
June 3, 1981 273-4o82
- ~
Mr. James P. O'Reilly, Director
- - g U. S. Nuclear Regulatory Commission Q'
Region II g'
g 1.t N' 101 Marietta Street, Suite 3.'00 J i [_O
,~
JUl p g yg
- - j Atlanta, Georgia 30303 T
Re: McGuire Nuclear Station Unit i EE****
Docket No. 50-369
%,/
Dear Mr. O'Reilly:
Please find attached Reportable Occurrence Report R0-369/81-77. This report concerns rejectable indications found in the vendor seal plate to door frame welds on the personnel locks.
This incident was considered to be of no significance with respect to the health and safety of the public.
Very truly yours,
/'
7 William O. Parker, Jr.
RWO:pw Attachment cc:
Director Mr. Bill Lavallee Office of Management and Program Analysis Nuclear Safety Analysis Center U. S. Nuclear Regulatory Corcmission
?. O. Box 10412 Washington, D. C.
Palo Alto, CA 94303 Ms. M. J. Graham Resident Inspector - NRC McGuire Nuclear Station 4 Q) 8107310368 810603 DR ADOCK 05000
\\
i McGUIRE NUCLEAR STATION INCIDENT REPORT Report Number:
81-77 Report Date:
. Tune 3, 1981 Occurrence Date: May 21, 1981 Facility: McGuire Nuclear Station Unit 1, Cornelius, N. C.
Introduction
An ASME Coda deviation was discovered during retrofitting and minor alteration work on the McGuire Nuclear Station Unit 1 personnel locks.
The personnel locks, therefore, not being in full Code compliance did not meet the specified requirements of the McGuire FSAR, Section 3.8.2.1 (2).
The deviation was first discovered en May 5, 1981.
Subsequent verification, evaluation and additional examination was conducted from May 5, 1981 to May 19, 1981.
The deviation was reported on Thursday, May 21, 1981 to Mr. Art Johnson of the NRC, Region II, by Mr. D. B. Lampke.
Background !nformation:
The four (4) personnel locks (two per unit) for the McCuire Nuclear Station were designed by the W. J. Woolley Company of River Forest, Illinois.
This company also supervised the fabrication of the locks by their subcontractor, Progressive Fabricators, Inc., of St. Louis, Missouri.
The general arrangement of the personnel locks is the same for all four locks.
The locks are Class B Vessels constructed and stamped in accordance with the 1968 ASME Ccde, including addenda through the summer of 1970.
Each personnel lock has fcur (4) inflatable seals per lock, two (2) for each door.
For the past several months, Duke Power Company, together with W. J.
Woolley Company and several inflatable seal manufacturers, have been working to solve a separate problem involving a number of seal failures. A part of the retrofitting related to the seal problem involved welding shim plates to the stainless steel seal plates en the door frames in order to minimize the seal closure gap.
Description of Deficiency: During nondestructive examination of the shim plate welds, Code rejectable indications were found in the vendot seal plate to door frame welds.
The vendor was contacted concerning the nature and examination requirements for these welds.
The welds were identified to be non-structural seal welds. A review of the Code of record by the Owner indicates that the welds in question require liquid penetrant (PT) or magnetic particle (MT) in-spection for full code compliance.
W. J. Woolley Company records indicated that the welds were inspected and accepted by the fabricator. However, when reinspected by the Owner, the welds did not pass the acceptance criteria.
Report Number:
81-77 Page 2 Safety Implications:
The welds to the seal plate are not structural welds, and are classified as seal welds only. As such the welds have no technical minimum size requirement and are only required to perform a sealing function.
Bypass leakage from containment can only occur if each weld has a thru-thickness defect.
Redundancy is accomplished by having two welds per seal, two seals per door and two doors per lock.
The welds in question have passed numerous leak rate tests.
In addition, they will be leak tested a minimum of once each 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during plant operation.
If leakage is detected in excess of that permitted by the plant Technical Specifications, standard procedures are in effect to locate and repair the source of the leakage.
Thus, standard plant operating procedures would have precluded excessive bypass leakage that could have caused a safety hazard.
Corrective Action
All seal plate welds for the " nit 1 McGuire personnel locks were PT inspected by the owner.
The inspection, including acceptance criteria, was done in accordance with the Owner's approved procedures and the ASME Code.
All rejectable indications were removed by grinding and/or welding and re-tested. All weld repairs were done in accordance wi+5 ASME Code requirements and were reviewed by the Authorized Code Inspector.
Following inspection and repair work, each air lock was pressure tested and leak rate tested to the requirements of the Station Technical Specifications.
The corresponding welds for the McGuire Unit 2 personnel locks will be in-spected, tested and repaired, as required.
This work will be completed by December 31, 1982.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000369/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000369/LER-1981-001-03, /03L-0:on 810129-0212,several Fire Detection Instruments Were Inoperable for Periods Exceeding 1-h. Caused by Const in Area.Fire Watches & Patrols Established | /03L-0:on 810129-0212,several Fire Detection Instruments Were Inoperable for Periods Exceeding 1-h. Caused by Const in Area.Fire Watches & Patrols Established | | | 05000369/LER-1981-002-01, /01T-0:on 810130,during Test,Vent Valve VX-41 & Containment Isolation Valve XV-40 Found Open to Atmosphere, in Violation of Tech Spec 4.9.4.1.Caused by Lack of Valve Checklist & Lack of Periodic Test.Valves Closed | /01T-0:on 810130,during Test,Vent Valve VX-41 & Containment Isolation Valve XV-40 Found Open to Atmosphere, in Violation of Tech Spec 4.9.4.1.Caused by Lack of Valve Checklist & Lack of Periodic Test.Valves Closed | | | 05000369/LER-1981-002, Forwards LER 81-002/01T-0 | Forwards LER 81-002/01T-0 | | | 05000369/LER-1981-003-03, /03L-0:on 810129,conventional Waste Plant Discharge Flow Monitor Found Inoperable.Caused by Inaccurate Flow Readings Due to Inability of Instrument to Measure Continuous Discharge Flow.New Equipment Ordered | /03L-0:on 810129,conventional Waste Plant Discharge Flow Monitor Found Inoperable.Caused by Inaccurate Flow Readings Due to Inability of Instrument to Measure Continuous Discharge Flow.New Equipment Ordered | | | 05000369/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000369/LER-1981-004-03, /03L-0:on 810129-0212,various Firestops & Fire Doors Found Inoperable for Periods Exceeding 1-h.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrols Established | /03L-0:on 810129-0212,various Firestops & Fire Doors Found Inoperable for Periods Exceeding 1-h.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrols Established | | | 05000369/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000369/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000369/LER-1981-005-03, /03L-0:on 810202,power Supply to Both Excore Range Monitors Was Interrupted.Caused by Maint Personnel Cutting Off Power to Investigate Steam Generator Status Lights & lo-lo Level Alarms.Personnel Instructed | /03L-0:on 810202,power Supply to Both Excore Range Monitors Was Interrupted.Caused by Maint Personnel Cutting Off Power to Investigate Steam Generator Status Lights & lo-lo Level Alarms.Personnel Instructed | | | 05000369/LER-1981-006-03, /03L-0:on 810202,leaking Seal Discovered on RHR Pump.Caused by Improperly Loaded Spring Which Holds Seal Faces Together.Seal Replaced | /03L-0:on 810202,leaking Seal Discovered on RHR Pump.Caused by Improperly Loaded Spring Which Holds Seal Faces Together.Seal Replaced | | | 05000369/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000369/LER-1981-007-03, /03L-0:on 810203,RHR Sys Train a Was Declared Inoperable.Caused by Draining Essential Header to Repair Leaking Valves in Nuclear Svc Water Sys.Valves Repaired & Train a Returned to Svc | /03L-0:on 810203,RHR Sys Train a Was Declared Inoperable.Caused by Draining Essential Header to Repair Leaking Valves in Nuclear Svc Water Sys.Valves Repaired & Train a Returned to Svc | | | 05000369/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000369/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000369/LER-1981-008-03, /03L-0:on 810203,control Area Ventilation Sys Train a Declared Inoperable.Caused by Draining Essential Header to Repair Leaking Valves in Nuclear Svc Water Sys. Valves Repaired & Train a Returned to Svc | /03L-0:on 810203,control Area Ventilation Sys Train a Declared Inoperable.Caused by Draining Essential Header to Repair Leaking Valves in Nuclear Svc Water Sys. Valves Repaired & Train a Returned to Svc | | | 05000369/LER-1981-009-03, /03L-0:on 810205,flow to Reactor Coolant Loops Was Momentarily Lost.Caused by Failure of Throttle Valve to Close Due to Loosening of Nut Holding Linkage to Valve Stem. Linkage Repositioned & Nut Tightened | /03L-0:on 810205,flow to Reactor Coolant Loops Was Momentarily Lost.Caused by Failure of Throttle Valve to Close Due to Loosening of Nut Holding Linkage to Valve Stem. Linkage Repositioned & Nut Tightened | | | 05000369/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Encl | Forwards LER 81-009/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000369/LER-1981-010-03, /03L-0:on 810207,total RHR Flow Exceeded Tech Specs.Caused by Air Line Supplying Actuator on RHR Valve Breaking,Allowing Valve to Fail Open.Rhr Flow Reset.Rigid Air Supply Lines to Be Replaced W/Flexible Lines | /03L-0:on 810207,total RHR Flow Exceeded Tech Specs.Caused by Air Line Supplying Actuator on RHR Valve Breaking,Allowing Valve to Fail Open.Rhr Flow Reset.Rigid Air Supply Lines to Be Replaced W/Flexible Lines | | | 05000369/LER-1981-011-03, /03T-0:on 810210,both Pressure Seals on Inner Door of Lower Personnel Air Lock Failed.Caused by Hole in One Seal & Bubble in Other Seal.Seals Replaced & Returned to Manufacturer | /03T-0:on 810210,both Pressure Seals on Inner Door of Lower Personnel Air Lock Failed.Caused by Hole in One Seal & Bubble in Other Seal.Seals Replaced & Returned to Manufacturer | | | 05000369/LER-1981-011, Forwards LER 81-011/03T-0 | Forwards LER 81-011/03T-0 | | | 05000369/LER-1981-012-03, /03T-0:on 801211,isolation Valve NV-250 Found Not Verified Closed Under Administrative Control Per Tech Spec. Caused by Lack of Signoff Step in Daily Surveillance Items. Procedure Change Incorporated | /03T-0:on 801211,isolation Valve NV-250 Found Not Verified Closed Under Administrative Control Per Tech Spec. Caused by Lack of Signoff Step in Daily Surveillance Items. Procedure Change Incorporated | | | 05000369/LER-1981-012, Forwards LER 81-012/03T-0 | Forwards LER 81-012/03T-0 | | | 05000369/LER-1981-013-03, /03L-0:on 810212,radiation Detectors EMF 33,35,36, 37,38,39 & 40 Were Declared Inoperable Due to Loss of Sample Flows.Caused by Individual Nonrelated Failures of Each Emf. Repairs Performed & EMFs Declared Operable | /03L-0:on 810212,radiation Detectors EMF 33,35,36, 37,38,39 & 40 Were Declared Inoperable Due to Loss of Sample Flows.Caused by Individual Nonrelated Failures of Each Emf. Repairs Performed & EMFs Declared Operable | | | 05000369/LER-1981-013, Forwards LER 81-013/03L-0.Detailed Event Analysis Encl | Forwards LER 81-013/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-014, Forwards LER 81-014/03L-0 | Forwards LER 81-014/03L-0 | | | 05000369/LER-1981-014-03, /03L-0:on 810212,while in Mode 6,control Room Received High Groundwater Alarm.Caused by Localized Temporary High Groundwater Level.Proper Surveillance Conducted & Alarm Was Cleared within 2 Days | /03L-0:on 810212,while in Mode 6,control Room Received High Groundwater Alarm.Caused by Localized Temporary High Groundwater Level.Proper Surveillance Conducted & Alarm Was Cleared within 2 Days | | | 05000369/LER-1981-015-03, /03L-0:on 810213,various Firestops & Fire Doors Rendered Inoperable for Periods Exceeding 1-h from 810213-27.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrols Established as Required | /03L-0:on 810213,various Firestops & Fire Doors Rendered Inoperable for Periods Exceeding 1-h from 810213-27.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrols Established as Required | | | 05000369/LER-1981-015, Forwards LER 81-015/03L-0 | Forwards LER 81-015/03L-0 | | | 05000369/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000369/LER-1981-016-03, /03L-0:on 810216,several Firestops Inadvertently Left Open W/O Fire Watches Being Posted.Caused by Omission of Stops from Maint List of Those Requiring Seals.Stops Sealed.Seals Will Be Verified Every 18 Months | /03L-0:on 810216,several Firestops Inadvertently Left Open W/O Fire Watches Being Posted.Caused by Omission of Stops from Maint List of Those Requiring Seals.Stops Sealed.Seals Will Be Verified Every 18 Months | | | 05000369/LER-1981-018, Forwards LER 81-018/03L-0.Detailed Event Analysis Encl | Forwards LER 81-018/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-018-03, /03L-0:on 810219,annunciator Alarm Indicated Loss of Sample Flow on Radiation Monitor 1-EMF-33.Monitor Vacuum Pump Internally Damaged Due to Water Inside Pump.Pump Vanes & Bearings Replaced & Water Removed | /03L-0:on 810219,annunciator Alarm Indicated Loss of Sample Flow on Radiation Monitor 1-EMF-33.Monitor Vacuum Pump Internally Damaged Due to Water Inside Pump.Pump Vanes & Bearings Replaced & Water Removed | | | 05000369/LER-1981-019-01, /01T-0:on 810306,during ESF Testing,Loss of Ac Power Was Experienced on Half of Station Security Sys.Caused by Blown Security Sys Power Inverter Fuse.Security Procedures Changed to Indicate Info Concerning Power Sys | /01T-0:on 810306,during ESF Testing,Loss of Ac Power Was Experienced on Half of Station Security Sys.Caused by Blown Security Sys Power Inverter Fuse.Security Procedures Changed to Indicate Info Concerning Power Sys | | | 05000369/LER-1981-019, Forwards LER 81-019/01T-0 | Forwards LER 81-019/01T-0 | | | 05000369/LER-1981-020, Forwards LER 81-020/03L-0.Detailed Event Analysis Encl | Forwards LER 81-020/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-020-03, /03L-0:on 810219,spurious High Radiation Alarm & Loss of Flow Alarm Sounded in Control Room on EMF-49. Personnel Cleared Radiation Alarm But Overlooked Closed Valve,Causing Loss of Flow Alarm.Monitor Repaired | /03L-0:on 810219,spurious High Radiation Alarm & Loss of Flow Alarm Sounded in Control Room on EMF-49. Personnel Cleared Radiation Alarm But Overlooked Closed Valve,Causing Loss of Flow Alarm.Monitor Repaired | | | 05000369/LER-1981-021, Forwards LER 81-021/03L-0.Detailed Event Analysis Encl | Forwards LER 81-021/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1981-021-03, /03L-0:on 810226,noble Gas Activity Monitor for Condenser Evacuation Sys EMF-33 Not Functioning.Caused by Excessive Amounts of Condensation in Sample Lines.Moisture Removed.Different Type of Moisture Separator to Be Used | /03L-0:on 810226,noble Gas Activity Monitor for Condenser Evacuation Sys EMF-33 Not Functioning.Caused by Excessive Amounts of Condensation in Sample Lines.Moisture Removed.Different Type of Moisture Separator to Be Used | | | 05000369/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000369/LER-1981-022-03, /03L-0:on 810301-16,various Portions of Fire Detection Sys Inoperable for Periods Exceeding 1-h.Caused by Const in Area.Fire Watches & Patrols Established as Required | /03L-0:on 810301-16,various Portions of Fire Detection Sys Inoperable for Periods Exceeding 1-h.Caused by Const in Area.Fire Watches & Patrols Established as Required | | | 05000369/LER-1981-023-03, /03L-0:on 810227-0313,various Firestops & Fire Doors Inoperable for Periods Exceeding 1-h.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrol Established as Required | /03L-0:on 810227-0313,various Firestops & Fire Doors Inoperable for Periods Exceeding 1-h.Caused by Const in & Through Areas Normally Closed Off.Fire Watches & Patrol Established as Required | | | 05000369/LER-1981-023, Forwards LER 81-023/03L-0 | Forwards LER 81-023/03L-0 | | | 05000369/LER-1981-024, Forwards LER 81-024/01T-0 | Forwards LER 81-024/01T-0 | | | 05000369/LER-1981-024-01, /01T-0:on 810316,Unit 1 Wedge Plates Discovered to Be Smaller than Required Size.Cause Not Stated.Calculations Reviewed to Determine Acceptance.Corrective Action Deemed Necessary.Bar Along Length of Washer Plate Added | /01T-0:on 810316,Unit 1 Wedge Plates Discovered to Be Smaller than Required Size.Cause Not Stated.Calculations Reviewed to Determine Acceptance.Corrective Action Deemed Necessary.Bar Along Length of Washer Plate Added | | | 05000369/LER-1981-025-01, /01T-0:on 810319,no Seismic Bracing or Calculations Found for 12 Reactor Bldg safety-related Electrical Cable Tray Hanger Stds.Cause Not Stated.Seismic Calculations Performed on Affected Hangers | /01T-0:on 810319,no Seismic Bracing or Calculations Found for 12 Reactor Bldg safety-related Electrical Cable Tray Hanger Stds.Cause Not Stated.Seismic Calculations Performed on Affected Hangers | | | 05000369/LER-1981-025, Forwards LER 81-025/01T-0 | Forwards LER 81-025/01T-0 | | | 05000369/LER-1981-026-03, /03L-0:on 810305,EMF Sys Panel Alarm in Control Room Indicated Malfunction of EMF-43A.Alarm Could Not Be Cleared & Control Room Outside Air Intake Gaseous Activity Monitor Inoperable.Caused by Broken Bnc Jack | /03L-0:on 810305,EMF Sys Panel Alarm in Control Room Indicated Malfunction of EMF-43A.Alarm Could Not Be Cleared & Control Room Outside Air Intake Gaseous Activity Monitor Inoperable.Caused by Broken Bnc Jack | | | 05000369/LER-1981-026, Forwards LER 81-026/03L-0.Detailed Event Analysis Encl | Forwards LER 81-026/03L-0.Detailed Event Analysis Encl | |
|