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| {{Adams | | {{Adams |
| | number = ML20195E917 | | | number = ML20206U416 |
| | issue date = 06/03/1999 | | | issue date = 05/10/1999 |
| | title = Confirms Conversation with Bradshaw on 990526 Re Rescheduling 990607 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Repts 50-413/99-10 & 50-414/99-10.Conference Will Be on 990623 in Atlanta,Ga | | | title = Insp Repts 50-413/99-10 & 50-414/99-10 on 990314-0424. Violation Being Considered for Escalated Enforcement Action Noted.Major Areas Inspected:Operations |
| | author name = Ogle C | | | author name = |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| | addressee name = Peterson G | | | addressee name = |
| | addressee affiliation = DUKE POWER CO. | | | addressee affiliation = |
| | docket = 05000413, 05000414 | | | docket = 05000413, 05000414 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = EA-99-094, EA-99-94, NUDOCS 9906140137 | | | document report number = 50-413-99-10, 50-414-99-10, NUDOCS 9905250204 |
| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | package number = ML20206U413 |
| | page count = 3 | | | document type = INSPECTION REPORT, NRC-GENERATED, TEXT-INSPECTION & AUDIT & I&E CIRCULARS |
| | | page count = 7 |
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| | U.S. NUCLEAR REGULATORY COMMISSION |
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| | ==REGION II== |
| | Docket Nos: 50-413, 50-414 License Nos: NPF-35, NPF-52 |
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| | Report Nos.: 50-413/99-10,50-414/99-10 Licensee: Duke Energy Corporation System: Catawba Nuclear Station, Units 1 and 2 Location: 422 South Church Street Charlotte, NC 28242 Dates: March 14 through April 24,1999 Inspectors: D. Roberts, Senior Resident inspector R. Franovich, Resident inspector Approved by: C. Ogle, Chief Reactor Projects Branch 1 Division of Reactor Projects |
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| | Enclosure |
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| June 3,1999 EA 99-094 Duke Energy Corporation ATTN: Mr. G. Si+e Vice President Catawba Nuclear Station
| | 9905250204 990510 PDR ADOCK 05000413 G PDR |
| , 4800 Concord Road York, SC 29745'- | | |
| SUBJECT: PREDECISIONAL ENFORCEMENT CONFERENCE - CATAWBA NUCLEAR STATION (RESCHEDULED)
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| | EXECUTIVE SUMMARY Catawba Nuclear Station, Units 1 and 2 NRC Inspection Report 50-413/99-10,50-414/99-10 This specialinspection focused on the integrated efforts of the Catawba Nuclear Station staff to evaluate, determine the root cause of, and correct a licensee-identified configuration control problem affecting the Standby Shutdown System from December 16 through 29,1998. The report covers the resident inspection period from March 14 to April 24,1999. [ Applicable template codes and the assessment for items inspected are provided below.) |
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| ==Dear Mr. Peterson:==
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| This letter confirms my conversation with Mr. S. Bradshaw of your staff on May 26,1999, conceming rescheduling the June 7,1999, predecisional enforcement conference to discuss the apparent violation described in inspection Report 50-413,414/99-10 that is associated with the potentialinoperability of the Standby Shutdown System. The conference will now be conducted on June 23,1999, from 9:00 a.m. to 11:00 a.m. in Room 24T20 of the Sam Nunn Atlanta Federal Center,61 Forsyth Street, S. W., Atlanta, Georgia. This will be an open meeting as per Section V of the " General Statement of Policy and Procedures for NRC Enforcement Actions," | | - |
| NUREG-1600.
| | An apparent violation of previous Technical Specification 3.7.13 [now Selected Licensee Commitment item 16.7-9 (Standby Shutdown System)] was identified concerning two mispositioned electrical circuit breakers that rendered the Standby Shutdown System inoperable from December 16 through 29,1998. This issue affected both Catawba unit (Section 02.1; [1 A - eel]) |
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| | Upon discovery of the mispositioned breakers, licensee personnel promptly restored the Standby Shutdown System to operable status and made appropriate notifications to the NRC in the time period required. (Section O2.1; [1 A, 5A - POS]) |
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| | The licensee's procedures for operating the Standby Shutdown System during certain flood, power, fire, and security events were adequate to maintain equipment protection and perform their intended functions. Only minor enhancements were neede Licensee personnel interviewed were knowledgeable of these procedures and how to implement them. (Section O3.1; [1C,38 - POS)) |
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| | The licensee's root cause evaluation provided in Licensee Event Report (LER) i 50-413/98-19 sufficiently developed human performance issues that resulted in the j mispositioned Standby Shutdown System breakers. The licensee adequately addressed possible contributing factors in its corrective action program. (Section 08.1; [5B - POS]) |
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| Should you have any questions conceming this meeting, please contact me at (404) 5d2-4610.
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| | .c Report Details Summary of Plant Status During the period of this event (December 16 through 29,1998) both units were at approximately 100 percent reactor powe . Operations 02 Operational Status of Facilities and Equipment O2.1 Standby Shutdown SystemlSSS) Inocerable Due to Personnel Error Durina Eauipment Restoration Process Inspection Scope (71707) |
| | The inspectors reviewed the circumstances associated with LER 50413/98-19 (previously discussed in inspection Report 50-413,414/98-12), in which the SSS was determined to be inoperable for nearly two weeks because two circuit breakers in a SSS motor control center were misaligned. The inspectors discussed this issue with plant personnel, reviewed SSS operating and test procedures, reviewed the restoration procedure associated with SSS maintenance activities on December 16,1998, and reviewed the licensee's immediate corrective actions for restoring system operabilit Observations and Findinas On December 29,1998, the licensee discovered that two breakers associated with the SSS were open when they should have been closed. The breakers were F02C, Motor Control Center 1EMXS Attemate Supply, and R03D, Motor Control Center 2EMXS Alternate Supply. With the two breakers open, the SSS was inoperable for Units 1 and 2. The licensee determined that the two breakers had been in the incorrect position for 13 days, which exceeded the allowed outage time of seven days before action to initiate a unit shutdown to Mode 3 (hot standby) was required within the following six hour SSS Backaround information The SSS is a non-safety-related system that is used to cope with certain flood, power, fire, and security events in order to achieve and maintain hot standby condition for one or both units. The SSS is utilized for certain events that may result in the loss of normal reactor coolant pump (RCP) seal injection. This involves a time-critical task to provide sealinjection with the associated unit's standby makeup pump (which can be powered from 1SLXG using the SSS diesel) within 10 minutes in order to maintain RCP seal integrity. Some of the SSS loads are supplied from 1(2)EMXS, which is normally aligned to the A train 4160 volt alternating current (VAC) vital electrical bus. Procedure OP/0/B/6100/013, Standby Shutdown System Operations, Revision 41, directs operators to open breaker 1(2) F01 A associated with 1(2)EMXA, which is powered from 1(2) ETA (the A train 4160 VAC vital bus), and close breaker 1(2)F03A associated with 1SLXG, the auxiliary power supply, during postulated events. If power to 1SLXG is lost, the SSS diesel engine will be manually started to power the SSS loads, assuming the required breaker alignment is in place. The standby makeup pump suction and discharge isolation valves are powered from 1(2)EMXS. These valves are normally closed and would not be capable of opening and providing RCP sealinjection with breakers F02C and R03D open since they are in series with breaker 1(2)F03A, respectivel ., |
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| , | | To ensure that the time-critical task of providing RCP seal injection can be performed within 10 minutes, the licensee has procedurally minimized the number of breakers that need to be manipulated (only F01 A and F03A) to transfer power to 1SLXG. With no procedural steps provided to verify that the third breaker (F02C for Unit 1 and R03D for Unit 2) was closed, the ability to provide reactor coolant pump seal injection within 10 l minutes could not be ensure Personnel Error Durino Eouioment Restoration Procedure Devetooment The licensee determined that breakers F02C and R03D had been left in the open position following preventive maintenance on December 16,1998. The normally closed breakers were tagged and placed in the OFF (open) position in support of the maintenance. Following completion of the maintenance activities, the tags were removed from the breakers, but the breakers were left in the OFF position in accordance with the system restoration procedure, Tag-Out 08-2811. The system restoration procedure incorrectly specified that the breakers be restored in the open position. The licensee determined that a senior reactor operator (SRO) who generated the restoration procedure assumed that, since the breaker was associated with an alternate power supply, then the normal position of the breaker was OFF. This SRO failed to reference applicable procedures to verify the normal breaker position. A second SRO reviewed and approved the tag-out procedure and missed the error. The misaligned breakers were identified and questioned by another operator on December 29,1998, who was performing an unrelated procedure validation walk-throug Operation Management Procedure (OMP) 2-18, Tagout Removal and Restoration Procedure, Revision 50, Step 6.2, Restoration / Partial Restore Record Sheet, item AA, states that equipment is to be normally returned to the position specified by a governing operating procedure checklist, the body of a goveming procedure, or as specified by the approving SRO based on plant conditions. The i.ispectors determined that the governing operating checklists for the two SSS breakers were not reviewed when the operators determined the required restored positions. Discussions with licensee personnel and review of assot nd Problem Investigation Process report (PIP) |
| | O-C98-4935, revealed that othen possible contributing factors included the fact that the restoration procedure did not reference OP/1/A/6350/001, Normal Power Checklist, which specifies the normal operating positions of the breakers; and station drawings did not accurately depict the breakers' normal operating positions. The inspectors concluded that these contributors did not cause the human performance error when the clearance restoration procedure was being developed and approved by the SROs in support of the December 16,1998, maintenance activities. These items were, however, properly included in the licensee's corrective action progra Root Cause Determination The licensee determined that the root cause for this event was inadequate work practices. Operations personnel failed to follow the established practice of reviewing OP/1/A/6350/001, Normal Power Checklist, to determine the correct normal (restored) |
| | position of breakers F02C and R03D. Based on the breakers' labels, operations personnel wrongly assumed that the normal position of the breakers was open. The inspectors concluded that the licensee's root cause determination, as well as its development of possible contributing factors in the corrective action program, was |
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| Sincerely, (Orig. Signed By Charles R. Ogle)
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| Charles R. Ogle, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 50-413, 50-414 b License Nos. NPF-35, NPF-52 I cc: G. D. Gilbert Regulatory Compliance Manager Duke Energy Corporation 4800 Concord Road York, SC 29745-9635 Lisa Vaughn Legal Department (PB05E)
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| Duke Energy Corporation 422 South Church Street Charlotte, NC 28242 cc cont: (See page 2) OFFICIAL COPY
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| 9906140137 990603 PDR ADOCK 05000413 C PDR j
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| | comprehensive. Several short- and long-term corrective actions were specified to restore operability and prevent recurrence. These included specifying, in the equipment data base and locally at the breakers, that having them in the OFF (open) position would render the SSS inoperable. Other actions were taken to address the human performance issue Safety Sianificance |
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| | The SSS is not considered safety-related. However, the SSS provides an alternate and independent means for maintaining the plant in a safe shutdown (for the SSS this is Hot . |
| | Standby [ Mode 3]) condition following certain loss of power, flooding, fire, and security events that result in the loss of normal RCP seal injection. These events are not , |
| | assumed to be concurrent with a design basis accident. Safe shutdown is achieved when: (1) the reactor is prevented from achieving criticality; and (2) adequate heat sink is provided to ensure reactor coolant system pressure and temperature design and safety limits are not exceeded. Upon a loss of normal RCP sealinjection, the SSS is placed in service and the associated unit's standby makeup pump is started to provide seal injection. This is to be accomplished within 10 minutes to ensure that significant RCP seal damage and a resultant small break loss of coolant accident do not occu With breakers F02C and R03D in the wrong positions and not referenced in the SSS operating procedure, the SSS's ability to perform its intended safety function of maintaining RCP seal integrity could not be ensure Reculatory Sianificance The inspectors concluded that the SSS was inoperable from December 16 through 29, 1998, without appropriate actions being taken to restore operability within seven days or perform a plant shutdown within the following six hours as required by Technical Specifications (TS). [As of January 16,1999, following the licensee's conversion to improved TS, this requirement was transferred to the Selected Licensee Commitments (SLC) document (item 16.7-9), considered Chapter 16 of the Catawba Updated Final Safety Analysis Report.) The licensee's failure to restore SSS operabiity or perform a plant shutdown within allowed outage times is considered an apparent violation of previous TS 3.7.13. This is identified as apparent violation (eel) 50-413,414/99-10-01: |
| | Standby Shutdown System Inoperable in Excess of TS Limits Due to Mispositioned Circuit Breaker c. Conclusions An apparent violation of previous Technical Specification 3.7.13 [now Selected Licensee Commitment item 16.7-9 (Standby Shutdown System)) was identified concerning two mispositioned electrical circuit breakers that rendered the Standby Shutdown System inoperable from December 16 through 29,1998. This issue affected both Catawba unit Upon discovery of the mispositioned breakers, licensee personnel promptly restored the Standby Shutdown System to operable status and made appropriate notifications to the NRC in the time period require j J |
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| DECL 2 cc cont'd:
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| Anne Cottingham Winston and Strawn 1400 L Street, NW Washington, D. C. 20005 North Carolina MPA-1 Suite 600 P. O. Box 29513 Raleigh, NC 27626-0513 Virgil R. Autry, Director Div. of Radioactive Waste Mgmt.
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| S. C. Department of Health and Environmental C^ontrol 2600 Bull Street Columbia, SC 29201 Richard P. Wilson, Esq. 4 Assistant Attorney General '
| | 03 Operations Procedures and Documentation O3.1 SSS Operatina Procedures and Plant Staff Knowledae - General Comments (71707) |
| S. C. Attomey General's Office P. O. Box 11549 -
| | The inspectors reviewed procedures associated with the operation of the SSS for loss of nuclear service water, loss of component cooling water, and station blackout events (i.e., events resulting in loss of normal RCP seal injection), and interviewed operations and security personnel responsible for implementation. One minor discrepancy was identified in OP/0/B/6100/013, Standby Shutdown System Operations, Revision 4 Procedural steps goveming the transfer to the SSS referenced a wrong structural |
| Columbia, SC 29211
| | ' column identification number in describing a critical terminal box location. This item was communicated to station personnel for correctio Otherwise, the licensee's procedures for operating the SSS during certain flood, power, |
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| | . fire, and security events were adequate to maintain equipment protection and perform their intended functions. Licensee personnel interviewed were knowledgeable of these procedures and how to implement the Miscellaneous Operations issues (40500, 92901) |
| Elaine Chan Federal Emergency Management Agency 500 C Street, SW, Room 840 i Washington, D. C. - 20472
| | - 08.1 - (Closed) LER 50-413/98-19-00: Standby Shutdown System inoperable in Excess of Technical Specification Allowed Outage Time due to Mispositioned Breakers Caused by Personnel Error The licensee's root cause evaluation provided in this LER sufficiently developed human - |
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| | performance issues that resulted in the mispositioned breakers. The licensee adequately addressed possible contributing factors in its corrective action progra Based on the inspectors' review of the subject event, as described in Sections 02 and |
| North Carolina Electric Membership Corporation P. O. Box 27306 Raleigh, NC 27611 Peggy Force .
| | ' 03 of this inspection report, this LER is close V. Management Meetmgs X1 Exit Meeting Summary The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on May 3,1999. The licensee acknowledged the findings presented. No proprietary information was identife . |
| Assistant Attomey General
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| ~ N. C. Department of Justice P. Boy 629 Raleigh, NC 27602 | |
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| - Saluda River Electric Cooperative, Inc.
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| P. O. Box 929 Laurens, SC 129360
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| cc cont'd: (See page 3)
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| | PARTIAL LIST OF PERSONS CONTACTED Licensee R. Beagles, Safety Assurance Manager M. Boyle, Radiation Protection Manager S. Bradshaw, Safety Assurance Manager G. Gilbert, Regulatory Compliance Manager * |
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| | R. Glover, Operations Superintendent P. Herran, Engineering Manager R. Jones, Station Manager G. Peterson, Catawba Site Vice-President F. Smith, Chemistry Manager R. Parker, Maintenance Manager INSPECTION PROCEDURES USED IP 40500: Effectiveness of Licensee Controls in identifying, Resolving, and Preventing Problems IP 71707: Plant Operations IP 92901: Followup - Operations ITEMS OPENED, CLOSED, AND DISCUSSED Opened 50-413,414/99-10-01 eel Standby Shutdown System inoperable in Excess of TS Liro;ts Due to Mispositioned Circuit Breakers (Secuon O2.1) |
| DEC' 3
| | Qloped 50-413/98-19-00 LER Standby Shutdown System inoperable in Excess of Technical Specification Allowed Outage Time due to Mispositioned Breakers Caused by Personnel Error (Section 08.1) |
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| | LIST OF ACRONYMS USED CFR - - Code of Federal Regulations eel - |
| cc cont'd: l County Manager of York County ;
| | Escalated Enforcement item (Apparent Violation) |
| York County Courthouse l York, SC 29745
| | LER - |
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| | Licensee Event Report NRC - |
| Piedmont Municipal Power Agency 121 Village Drive Greer, SC 29651 ,
| | Nuclear Regulatory Commission PIP - Problem Investigation Process RCP - |
| L. A. Keller, Manager Nuclear Regulatory Licensing Duke Energy Corporation
| | Reactor Coolant Pump SLC - |
| - 526 S. Church Street Charlotte, NC 28201-0006
| | Selected Licensee Commitments SRO - |
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| | Senior Reactor Operator SSS - |
| Steven P. Shaver l Senior Sales Engineer l Westinghouse Electric Company 5929 Carnegie Boulevard, Suite 500 Charlotte, NC 28209 Distribution:
| | Standby Shutdown System TS- - |
| . Hard Paoer Coov Region 11 Regional Coordinator OEDO (16E15)
| | Technical Specification , |
| L. Plisco, Ril P. Tam, NRR R. Carroll, Rll C. Payne, Rll PUBLIC NRC Resident inspector U.S. Nuclear Regulator Commission 4830 Concord Road York, SC 29745 j
| | VAC - Volts Attemating Current |
| . E-Mail Meeting Announcement Coordinator, OADM/DFIPS (PMNS) ,
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| Region ll Administrator's Secretary l DRP Division Secretary
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| Region ll Division Directors and Deputies Regional Counsel Region ll Public Affairs Officer Region ll RMB Chief I Chief, RAB, AEOD Headquarters Operations Officer OFFICE Rit:Dl3P slGNATuRE Mgm NAME Ruin 6rQw DATE ,Af,/ /99 6f 199 El /99 El /99 61 /99 6/ 199 6I /99 COPY? fi YEs'l NO YEs No YEs NO YEs No YEs No YEs No YEs No Of8EJCIA'L RECORD COPY DOCUMENT NAME: G:\CATM1G623.WPD L
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Category:INSPECTION REPORT
MONTHYEARIR 05000413/19990051999-09-24024 September 1999 Insp Repts 50-413/99-05 & 50-414/99-05 on 990718-0828. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19990041999-08-13013 August 1999 Insp Repts 50-413/99-04 & 50-414/99-04 on 990606-0717. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20209E2831999-07-0101 July 1999 Insp Repts 50-413/99-03 & 50-414/99-03 on 990425-0605. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000413/19990111999-06-0202 June 1999 Insp Repts 50-413/99-11 & 50-414/99-11 on 990422-23 & 0503. No Violations Noted.Major Areas Inspected:Licensee Identified Frost & Ice Buildup Which Affected Unit 1 Ice Condenser Lower Inlet Doors IR 05000413/19990021999-05-20020 May 1999 Insp Repts 50-413/99-02 & 50-414/99-02 on 990314-0424.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20206U4161999-05-10010 May 1999 Insp Repts 50-413/99-10 & 50-414/99-10 on 990314-0424. Violation Being Considered for Escalated Enforcement Action Noted.Major Areas Inspected:Operations IR 05000413/19990011999-04-0606 April 1999 Insp Repts 50-413/99-01 & 50-414/99-01 on 990124-0313. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19980121999-02-17017 February 1999 Insp Repts 50-413/98-12 & 50-414/98-12 on 981213-990123. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19980111999-01-11011 January 1999 Insp Repts 50-413/98-11 & 50-414/98-11 on 981101-1212.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19980151999-01-0404 January 1999 Insp Repts 50-413/98-15 & 50-414/98-15 on 981102-06 & 16-20. No Violations Noted.Major Areas Inspected:Licensee Corrective Action Program by Sampling Activities Defined in Nuclear Sys Directive 210,rev 1 IR 05000413/19980161998-12-0404 December 1998 Insp Repts 50-413/98-16 & 50-414/98-16 on 980915-1101.No Violations Rept Encl.Major Areas Inspected:Licensee Maint, Surveillance & Engineering Programs Involving Unit 2 Ice Condenser IR 05000413/19980101998-11-23023 November 1998 Insp Repts 50-413/98-10 & 50-414/98-10 on 980927-1031.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering & Plant Support ML20155B3821998-10-19019 October 1998 Insp Repts 50-413/98-13 & 50-414/98-13 on 980807-0915. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Review Ice Condenser Related Problems,Which Led to Forced Shutdown IR 05000413/19980081998-09-14014 September 1998 Insp Repts 50-413/98-08 & 50-414/98-08 on 980705-0815. Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000413/19980091998-08-26026 August 1998 Insp Repts 50-413/98-09 & 50-414/98-09 on 980816-0826. Examples of Two Apparent Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000413/19980071998-07-27027 July 1998 Insp Repts 50-413/98-07 & 50-414/98-07 on 980524-0704. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support,Including Physical Security IR 05000413/19980051998-06-22022 June 1998 Insp Repts 50-413/98-05 & 50-414/98-05 on 980412-0523.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19980061998-06-0505 June 1998 Insp Repts 50-413/98-06 & 50-414/98-06 on 980511-15. Violations Noted.Major Areas Inspected:Facts Surrounding Event Associated W/Degradation of CNS Unit Auxiliary Feedwater Sys During Rapid down-power on 980507 IR 05000413/19980031998-04-30030 April 1998 Insp Repts 50-413/98-03 & 50-414/98-03 on 980222-0411. Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Aspects of Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19980041998-04-20020 April 1998 Insp Repts 50-413/98-04 & 50-414/98-04 on 980302-06.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise for Plant ML20217G5661998-03-23023 March 1998 Insp Repts 50-413/98-01 & 50-414/98-01 on 980111-0221. Violations Noted.Major Areas Inspected:Operation,Maint, Engineering & Plant Support IR 05000413/19980021998-02-17017 February 1998 Partially Withheld Insp Repts 50-413/98-02 & 50-414/98-02 on 980112-13 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected:Plant Support,Including Malevolent Use of Vehicles at Plant ML20203L6301998-02-0909 February 1998 Insp Repts 50-413/97-15 & 50-414/97-15 on 971123-980110. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support ML20197F2861997-12-19019 December 1997 Insp Repts 50-413/97-14 & 50-414/97-14 on 971012-1122. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19970121997-11-10010 November 1997 Insp Repts 50-413/97-12 & 50-414/97-12 on 970831-1011. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support as Well as Results of Announced Inspection by Regional Security Inspector IR 05000413/19970111997-09-26026 September 1997 Insp Repts 50-413/97-11 & 50-414/97-11 on 970720-0830. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19970101997-09-11011 September 1997 Insp Repts 50-413/97-10 & 50-414/97-10 on 970623-0731.No Violations Noted.Major Areas Inspected:Licensee Calculations,Analysis & Other Engineering Documents ML20210N7341997-08-18018 August 1997 Insp Repts 50-413/97-09 & 50-414/97-09 on 970608-0719. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20149F9291997-07-0707 July 1997 Insp Repts 50-413/97-08 & 50-414/97-08 on 970427-0607. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20148F9441997-05-23023 May 1997 Insp Repts 50-413/97-07 & 50-414/97-07 on 970323-0426. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19970051997-04-21021 April 1997 Integrated Insp Repts 50-413/97-05 & 50-414/97-05 on 970216- 0322.No Violations Identified.Major Areas Inspected:Maint, Operations,Engineering & Plant Support IR 05000413/19970061997-04-0404 April 1997 Insp Repts 50-413/97-06 & 50-414/97-06 on 970317-20.No Violations Noted.Major Areas Inspected:Conduct of Security & Safeguards Activities,Plant Support & Status of Security Facilities & Equipment ML20140B7631997-03-17017 March 1997 Insp Repts 50-413/97-03 & 50-414/97-03 on 970112-0215. Violations Noted.Major Areas Inspected:Licensee Operation, Maint,Engineering & Plant Support IR 05000413/19960191997-02-21021 February 1997 Insp Repts 50-413/96-19 & 50-414/96-19 on 961007, 961127, & 970206.Violation Noted.Major Areas inspected:in-office Review of Licensee Describing Changes to CNS UFSAR Re Lack of Circuit Breaker Coordination for 600-Vac IR 05000413/19960201997-02-10010 February 1997 Insp Repts 50-413/96-20 & 50-414/96-20 on 961201-970111.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19970041997-01-31031 January 1997 Insp Repts 50-413/97-04 & 50-414/97-04 on 970106-23.No Violations Noted.Major Areas Inspected:Operations & Engineering IR 05000413/19970021997-01-31031 January 1997 Insp Repts 50-413/97-02 & 50-414/97-02 on 970106-10.No Violations Noted.Major Areas Inspected:Plant Support IR 05000413/19960181996-12-30030 December 1996 Insp Repts 50-413/96-18 & 50-414/96-18 on 961020-1130.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering ML20135C2601996-11-15015 November 1996 Insp Repts 50-413/96-16 & 50-414/96-16 on 960908-1019.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19960151996-11-0707 November 1996 Insp Repts 50-413/96-15 & 50-414/96-15 on 960901-1012.No Violations Noted.Major Areas Inspected:Engineering & Plant Support IR 05000413/19960171996-11-0101 November 1996 Insp Repts 50-413/96-17 & 50-414/96-17 on 960930-1004.No Violations Noted.Major Areas Inspected:Plant Support ML20128R0951996-10-0707 October 1996 Insp Repts 50-413/96-13 & 50-414/96-13 on 960728-0907. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering,Plant Support & Plant Status ML20128J0391996-09-30030 September 1996 Insp Repts 50-413/96-12 & 50-414/96-12 on 960804-31. Violations Noted.Major Areas Inspected:Engineering, Summary of Plant Status & Observations & Findings IR 05000413/19940141994-06-0303 June 1994 Insp Repts 50-413/94-14 & 50-414/94-14 on 940509-20.No Violations Noted.Major Areas Inspected:Isi & Flow Assisted Corrosion IR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts IR 05000413/19930321993-12-30030 December 1993 Insp Repts 50-413/93-32 & 50-414/93-32 on 931117-19 & 1129-1203.Violations Noted.Major Areas Inspected:Observation of Eddy Current (ET) Exam of SG Tubes,Inservice Activities Including Surface & Volumetric Exams,Review of Radiographs IR 05000413/19930331993-12-23023 December 1993 Insp Repts 50-413/93-33 & 50-414/93-33 on 931129-1203.No Violations Noted.Major Areas Inspected:Isi of Pipe Supports & Snubbers & TS Surveillance of Snubbers IR 05000413/19930311993-12-22022 December 1993 Insp Repts 50-413/93-31 & 50-414/93-31 on 931107-1204.No Violations Noted.Major Areas Inspected:Plant Operations, Maintenance,Engineering,Plant Support & follow-up of Previously Identifed Items IR 05000413/19930291993-12-12012 December 1993 Insp Repts 50-413/93-29 & 50-414/93-29 on 931115-19.No Violations Noted.Major Areas Inspected:Occupational Radiation Safety,Organization & Mgt Controls,Training & Qualification,Audits & Appraisals IR 05000413/19930281993-12-10010 December 1993 Insp Repts 50-413/93-28 & 50-414/93-28 on 931101-05.No Violations Noted.Deviation Noted.Major Areas Inspected: Adequacy of Licensee Programs,Procedures & Supporting Documentation for Implementation of Station Blackout Rule 1999-09-24
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000413/19990051999-09-24024 September 1999 Insp Repts 50-413/99-05 & 50-414/99-05 on 990718-0828. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19990041999-08-13013 August 1999 Insp Repts 50-413/99-04 & 50-414/99-04 on 990606-0717. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20209E2831999-07-0101 July 1999 Insp Repts 50-413/99-03 & 50-414/99-03 on 990425-0605. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000413/19990111999-06-0202 June 1999 Insp Repts 50-413/99-11 & 50-414/99-11 on 990422-23 & 0503. No Violations Noted.Major Areas Inspected:Licensee Identified Frost & Ice Buildup Which Affected Unit 1 Ice Condenser Lower Inlet Doors IR 05000413/19990021999-05-20020 May 1999 Insp Repts 50-413/99-02 & 50-414/99-02 on 990314-0424.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20206U4161999-05-10010 May 1999 Insp Repts 50-413/99-10 & 50-414/99-10 on 990314-0424. Violation Being Considered for Escalated Enforcement Action Noted.Major Areas Inspected:Operations IR 05000413/19990011999-04-0606 April 1999 Insp Repts 50-413/99-01 & 50-414/99-01 on 990124-0313. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19980121999-02-17017 February 1999 Insp Repts 50-413/98-12 & 50-414/98-12 on 981213-990123. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19980111999-01-11011 January 1999 Insp Repts 50-413/98-11 & 50-414/98-11 on 981101-1212.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19980151999-01-0404 January 1999 Insp Repts 50-413/98-15 & 50-414/98-15 on 981102-06 & 16-20. No Violations Noted.Major Areas Inspected:Licensee Corrective Action Program by Sampling Activities Defined in Nuclear Sys Directive 210,rev 1 IR 05000413/19980161998-12-0404 December 1998 Insp Repts 50-413/98-16 & 50-414/98-16 on 980915-1101.No Violations Rept Encl.Major Areas Inspected:Licensee Maint, Surveillance & Engineering Programs Involving Unit 2 Ice Condenser IR 05000413/19980101998-11-23023 November 1998 Insp Repts 50-413/98-10 & 50-414/98-10 on 980927-1031.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering & Plant Support ML20155B3821998-10-19019 October 1998 Insp Repts 50-413/98-13 & 50-414/98-13 on 980807-0915. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Review Ice Condenser Related Problems,Which Led to Forced Shutdown IR 05000413/19980081998-09-14014 September 1998 Insp Repts 50-413/98-08 & 50-414/98-08 on 980705-0815. Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000413/19980091998-08-26026 August 1998 Insp Repts 50-413/98-09 & 50-414/98-09 on 980816-0826. Examples of Two Apparent Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000413/19980071998-07-27027 July 1998 Insp Repts 50-413/98-07 & 50-414/98-07 on 980524-0704. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support,Including Physical Security IR 05000413/19980051998-06-22022 June 1998 Insp Repts 50-413/98-05 & 50-414/98-05 on 980412-0523.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19980061998-06-0505 June 1998 Insp Repts 50-413/98-06 & 50-414/98-06 on 980511-15. Violations Noted.Major Areas Inspected:Facts Surrounding Event Associated W/Degradation of CNS Unit Auxiliary Feedwater Sys During Rapid down-power on 980507 IR 05000413/19980031998-04-30030 April 1998 Insp Repts 50-413/98-03 & 50-414/98-03 on 980222-0411. Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Aspects of Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19980041998-04-20020 April 1998 Insp Repts 50-413/98-04 & 50-414/98-04 on 980302-06.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise for Plant ML20217G5661998-03-23023 March 1998 Insp Repts 50-413/98-01 & 50-414/98-01 on 980111-0221. Violations Noted.Major Areas Inspected:Operation,Maint, Engineering & Plant Support IR 05000413/19980021998-02-17017 February 1998 Partially Withheld Insp Repts 50-413/98-02 & 50-414/98-02 on 980112-13 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected:Plant Support,Including Malevolent Use of Vehicles at Plant ML20203L6301998-02-0909 February 1998 Insp Repts 50-413/97-15 & 50-414/97-15 on 971123-980110. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support ML20197F2861997-12-19019 December 1997 Insp Repts 50-413/97-14 & 50-414/97-14 on 971012-1122. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19970121997-11-10010 November 1997 Insp Repts 50-413/97-12 & 50-414/97-12 on 970831-1011. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support as Well as Results of Announced Inspection by Regional Security Inspector IR 05000413/19970111997-09-26026 September 1997 Insp Repts 50-413/97-11 & 50-414/97-11 on 970720-0830. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19970101997-09-11011 September 1997 Insp Repts 50-413/97-10 & 50-414/97-10 on 970623-0731.No Violations Noted.Major Areas Inspected:Licensee Calculations,Analysis & Other Engineering Documents ML20210N7341997-08-18018 August 1997 Insp Repts 50-413/97-09 & 50-414/97-09 on 970608-0719. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20149F9291997-07-0707 July 1997 Insp Repts 50-413/97-08 & 50-414/97-08 on 970427-0607. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20148F9441997-05-23023 May 1997 Insp Repts 50-413/97-07 & 50-414/97-07 on 970323-0426. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19970051997-04-21021 April 1997 Integrated Insp Repts 50-413/97-05 & 50-414/97-05 on 970216- 0322.No Violations Identified.Major Areas Inspected:Maint, Operations,Engineering & Plant Support IR 05000413/19970061997-04-0404 April 1997 Insp Repts 50-413/97-06 & 50-414/97-06 on 970317-20.No Violations Noted.Major Areas Inspected:Conduct of Security & Safeguards Activities,Plant Support & Status of Security Facilities & Equipment ML20140B7631997-03-17017 March 1997 Insp Repts 50-413/97-03 & 50-414/97-03 on 970112-0215. Violations Noted.Major Areas Inspected:Licensee Operation, Maint,Engineering & Plant Support IR 05000413/19960191997-02-21021 February 1997 Insp Repts 50-413/96-19 & 50-414/96-19 on 961007, 961127, & 970206.Violation Noted.Major Areas inspected:in-office Review of Licensee Describing Changes to CNS UFSAR Re Lack of Circuit Breaker Coordination for 600-Vac IR 05000413/19960201997-02-10010 February 1997 Insp Repts 50-413/96-20 & 50-414/96-20 on 961201-970111.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19970041997-01-31031 January 1997 Insp Repts 50-413/97-04 & 50-414/97-04 on 970106-23.No Violations Noted.Major Areas Inspected:Operations & Engineering IR 05000413/19970021997-01-31031 January 1997 Insp Repts 50-413/97-02 & 50-414/97-02 on 970106-10.No Violations Noted.Major Areas Inspected:Plant Support IR 05000413/19960181996-12-30030 December 1996 Insp Repts 50-413/96-18 & 50-414/96-18 on 961020-1130.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering ML20135C2601996-11-15015 November 1996 Insp Repts 50-413/96-16 & 50-414/96-16 on 960908-1019.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19960151996-11-0707 November 1996 Insp Repts 50-413/96-15 & 50-414/96-15 on 960901-1012.No Violations Noted.Major Areas Inspected:Engineering & Plant Support IR 05000413/19960171996-11-0101 November 1996 Insp Repts 50-413/96-17 & 50-414/96-17 on 960930-1004.No Violations Noted.Major Areas Inspected:Plant Support ML20128R0951996-10-0707 October 1996 Insp Repts 50-413/96-13 & 50-414/96-13 on 960728-0907. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering,Plant Support & Plant Status ML20128J0391996-09-30030 September 1996 Insp Repts 50-413/96-12 & 50-414/96-12 on 960804-31. Violations Noted.Major Areas Inspected:Engineering, Summary of Plant Status & Observations & Findings IR 05000413/19940141994-06-0303 June 1994 Insp Repts 50-413/94-14 & 50-414/94-14 on 940509-20.No Violations Noted.Major Areas Inspected:Isi & Flow Assisted Corrosion IR 05000269/19930321994-01-0606 January 1994 Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Major Areas Inpected:Licensee Safeguards Info Program to folow-up on Licensee Repts IR 05000413/19930321993-12-30030 December 1993 Insp Repts 50-413/93-32 & 50-414/93-32 on 931117-19 & 1129-1203.Violations Noted.Major Areas Inspected:Observation of Eddy Current (ET) Exam of SG Tubes,Inservice Activities Including Surface & Volumetric Exams,Review of Radiographs IR 05000413/19930331993-12-23023 December 1993 Insp Repts 50-413/93-33 & 50-414/93-33 on 931129-1203.No Violations Noted.Major Areas Inspected:Isi of Pipe Supports & Snubbers & TS Surveillance of Snubbers IR 05000413/19930311993-12-22022 December 1993 Insp Repts 50-413/93-31 & 50-414/93-31 on 931107-1204.No Violations Noted.Major Areas Inspected:Plant Operations, Maintenance,Engineering,Plant Support & follow-up of Previously Identifed Items IR 05000413/19930291993-12-12012 December 1993 Insp Repts 50-413/93-29 & 50-414/93-29 on 931115-19.No Violations Noted.Major Areas Inspected:Occupational Radiation Safety,Organization & Mgt Controls,Training & Qualification,Audits & Appraisals IR 05000413/19930281993-12-10010 December 1993 Insp Repts 50-413/93-28 & 50-414/93-28 on 931101-05.No Violations Noted.Deviation Noted.Major Areas Inspected: Adequacy of Licensee Programs,Procedures & Supporting Documentation for Implementation of Station Blackout Rule 1999-09-24
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000413/19993021999-10-12012 October 1999 NRC Operator Licensing Retake Exam Repts 50-413/99-302 & 50-414/99-302 (Including Completed & Graded Tests) for Tests Administered on 990921-23.Two Out of Three RO Candidates & One SRO Passed Retake Exam IR 05000413/19993011999-09-30030 September 1999 NRC Operator Licensing Exam Repts 50-413/99-301 & 50-414/99-301 (Including Completed & Graded Tests) for Tests Administered on 990524-27,0603,07-10 & 16.Eight of Fourteen Applicants Passed Exam IR 05000413/19990051999-09-24024 September 1999 Insp Repts 50-413/99-05 & 50-414/99-05 on 990718-0828. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19990041999-08-13013 August 1999 Insp Repts 50-413/99-04 & 50-414/99-04 on 990606-0717. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20210H2211999-07-22022 July 1999 Notice of Violation from Insp on 990314-0424.Violation Noted:Sss Was Not Inoperable for Thirteen Days Because Electrical Breakers Associated with SSS Motor Control Ctr Were Mispositioned ML20209E2831999-07-0101 July 1999 Insp Repts 50-413/99-03 & 50-414/99-03 on 990425-0605. Non-cited Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000413/19990111999-06-0202 June 1999 Insp Repts 50-413/99-11 & 50-414/99-11 on 990422-23 & 0503. No Violations Noted.Major Areas Inspected:Licensee Identified Frost & Ice Buildup Which Affected Unit 1 Ice Condenser Lower Inlet Doors IR 05000413/19990021999-05-20020 May 1999 Insp Repts 50-413/99-02 & 50-414/99-02 on 990314-0424.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support PNO-II-99-017, on 990515,indication of Main Generator Ground Fault Was Received While Performing Turbine Startup in Preparation for Placing Unit on Line.Licensee Is Conducting Investigation to Determine Actual Cause of Ground1999-05-18018 May 1999 PNO-II-99-017:on 990515,indication of Main Generator Ground Fault Was Received While Performing Turbine Startup in Preparation for Placing Unit on Line.Licensee Is Conducting Investigation to Determine Actual Cause of Ground ML20206U4161999-05-10010 May 1999 Insp Repts 50-413/99-10 & 50-414/99-10 on 990314-0424. Violation Being Considered for Escalated Enforcement Action Noted.Major Areas Inspected:Operations PNO-II-99-015, on 990503,shutdown in Excess of 72 H Occurred. Licensee Is Still Conducting Investigation Into Cause of Main Generator Protection Lockout & Making Preparations to Inspect & Remove Any Excessive Fouling from Inside Afws1999-05-0505 May 1999 PNO-II-99-015:on 990503,shutdown in Excess of 72 H Occurred. Licensee Is Still Conducting Investigation Into Cause of Main Generator Protection Lockout & Making Preparations to Inspect & Remove Any Excessive Fouling from Inside Afws IR 05000413/19990011999-04-0606 April 1999 Insp Repts 50-413/99-01 & 50-414/99-01 on 990124-0313. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20207A5881999-02-17017 February 1999 Notice of Violation from Insp on 981213-990123.Violation Noted:Licensee Made Change to Procedures as Described in Updated Final Safety Analysis Rept & Failed to Perform Written Safety Evaluation IR 05000413/19980121999-02-17017 February 1999 Insp Repts 50-413/98-12 & 50-414/98-12 on 981213-990123. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19980111999-01-11011 January 1999 Insp Repts 50-413/98-11 & 50-414/98-11 on 981101-1212.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19980151999-01-0404 January 1999 Insp Repts 50-413/98-15 & 50-414/98-15 on 981102-06 & 16-20. No Violations Noted.Major Areas Inspected:Licensee Corrective Action Program by Sampling Activities Defined in Nuclear Sys Directive 210,rev 1 IR 05000413/19980161998-12-0404 December 1998 Insp Repts 50-413/98-16 & 50-414/98-16 on 980915-1101.No Violations Rept Encl.Major Areas Inspected:Licensee Maint, Surveillance & Engineering Programs Involving Unit 2 Ice Condenser IR 05000413/19980101998-11-23023 November 1998 Insp Repts 50-413/98-10 & 50-414/98-10 on 980927-1031.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering & Plant Support ML20155B3821998-10-19019 October 1998 Insp Repts 50-413/98-13 & 50-414/98-13 on 980807-0915. Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Review Ice Condenser Related Problems,Which Led to Forced Shutdown ML20154C4301998-09-14014 September 1998 Notice of Violation from Insp on 980705-0815.Violation Noted:Licensee Failed to Establish Adequate Surveillance Procedures IR 05000413/19980081998-09-14014 September 1998 Insp Repts 50-413/98-08 & 50-414/98-08 on 980705-0815. Violations Noted.Major Areas Inspected:Operations,Maint & Engineering PNO-II-98-037A, on 980807,update Shutdown in Excess of 72 H Made.Licensee Has Cleaned & Satisfactorily Inspected IC Flow Channels.Licensee Identified Discrepancies in Bolting of IC Intermediate Deck Door Frames & Hinges.Conditions Addressed1998-08-28028 August 1998 PNO-II-98-037A:on 980807,update Shutdown in Excess of 72 H Made.Licensee Has Cleaned & Satisfactorily Inspected IC Flow Channels.Licensee Identified Discrepancies in Bolting of IC Intermediate Deck Door Frames & Hinges.Conditions Addressed IR 05000413/19980091998-08-26026 August 1998 Insp Repts 50-413/98-09 & 50-414/98-09 on 980816-0826. Examples of Two Apparent Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-II-98-037, on 980808,shutdown in Excess of 72 H Occurred. Licensee Inspected Approximately Half of Unit 2 Ice Condenser Bay Flow Channels from Intermediate Deck W/No Ice Obstructions in Excess of TS Limit Identified1998-08-10010 August 1998 PNO-II-98-037:on 980808,shutdown in Excess of 72 H Occurred. Licensee Inspected Approximately Half of Unit 2 Ice Condenser Bay Flow Channels from Intermediate Deck W/No Ice Obstructions in Excess of TS Limit Identified ML20236V7351998-07-27027 July 1998 Notice of Violation from Insp on 980524-0704.Violation Noted:Licensee Failed to Identify & Take Prompt C/A Following Unit 1 Upper Surge Tank over-temp Events on 960120,980111 & 0507 IR 05000413/19980071998-07-27027 July 1998 Insp Repts 50-413/98-07 & 50-414/98-07 on 980524-0704. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support,Including Physical Security IR 05000413/19980051998-06-22022 June 1998 Insp Repts 50-413/98-05 & 50-414/98-05 on 980412-0523.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20236J7471998-06-11011 June 1998 Notice of Violation from Insp on 980222-0411.Violation Noted:Adminstrative & Surveillance Procedures Not Implemented as Evidenced by Listed Examples IR 05000413/19980061998-06-0505 June 1998 Insp Repts 50-413/98-06 & 50-414/98-06 on 980511-15. Violations Noted.Major Areas Inspected:Facts Surrounding Event Associated W/Degradation of CNS Unit Auxiliary Feedwater Sys During Rapid down-power on 980507 PNO-II-98-025, on 980507,AFW Sys Declared Inoperable.Licensee Isolated Valves 1CM-127 & 2CM-127 in Units 1 & 2, Respectively,To Prevent Recurrence Until Permanent Corrective Actions Can Be Developed1998-05-11011 May 1998 PNO-II-98-025:on 980507,AFW Sys Declared Inoperable.Licensee Isolated Valves 1CM-127 & 2CM-127 in Units 1 & 2, Respectively,To Prevent Recurrence Until Permanent Corrective Actions Can Be Developed IR 05000413/19980031998-04-30030 April 1998 Insp Repts 50-413/98-03 & 50-414/98-03 on 980222-0411. Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Aspects of Licensee Operations, Maint,Engineering & Plant Support IR 05000413/19980041998-04-20020 April 1998 Insp Repts 50-413/98-04 & 50-414/98-04 on 980302-06.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise for Plant ML20217G5661998-03-23023 March 1998 Insp Repts 50-413/98-01 & 50-414/98-01 on 980111-0221. Violations Noted.Major Areas Inspected:Operation,Maint, Engineering & Plant Support ML20217G5551998-03-23023 March 1998 Notice of Violation from Insp on 980111-0221.Violation Noted:Licensee Failed to Perform Written Safety Evaluation for Closing Valves 1CA-6 & 2CA-6 IR 05000413/19980021998-02-17017 February 1998 Partially Withheld Insp Repts 50-413/98-02 & 50-414/98-02 on 980112-13 (Ref 10CFR2.790).No Violations Noted.Major Areas Inspected:Plant Support,Including Malevolent Use of Vehicles at Plant ML20203L6301998-02-0909 February 1998 Insp Repts 50-413/97-15 & 50-414/97-15 on 971123-980110. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support ML20203L6251998-02-0909 February 1998 Notice of Violation from Insp on 971123-980110.Violation Noted:Changes to Radiological Conditions in 1B Residual Heat Removal Pump Room Not Logged to Reflect Changes in Dress Requirements ML20199L6301998-02-0202 February 1998 Notice of Violation from Insp & Exam on 971117-21 & 971201-19.Violation Noted:As of 971219,selected Officers from Site Security Force Had Not Been Retrained to Perform non-licensed Operator Emergency Tasks for Starting Ssf PNO-II-97-066, on 971230,RCS Leakage Requiring Forced Unit Cooldown Occurred.No Radioactive Release Outside of Reactor Containment Facilities Due to Leakage.Licensee Informed States on Nc & Sc1997-12-31031 December 1997 PNO-II-97-066:on 971230,RCS Leakage Requiring Forced Unit Cooldown Occurred.No Radioactive Release Outside of Reactor Containment Facilities Due to Leakage.Licensee Informed States on Nc & Sc PNO-II-97-064, on 971229,inadvertent Safety Injection Occurred Due to Operators Failing to Perform Step Which Resulted in Cold Leg Injection Valve Being Left Open. Licensee Engineers Performing Evaluation1997-12-29029 December 1997 PNO-II-97-064:on 971229,inadvertent Safety Injection Occurred Due to Operators Failing to Perform Step Which Resulted in Cold Leg Injection Valve Being Left Open. Licensee Engineers Performing Evaluation ML20197F2481997-12-19019 December 1997 Notice of Violation from Insp on 971012-1122.Violation Noted:Licensee Failed to Follow Radiation Protection Procedures in That,Current Radiation Dose Rates Were Not on Vacuum Cleaner Label as Required IR 05000414/19970081997-12-19019 December 1997 Notice of Deviation from Insp on 971012-1122.Deviation Noted:On 971020,licensee Had Not Performed Alarm Set Point Adjustment Evaluation Discussed in Violation 50-414/97-08-01 ML20197F2861997-12-19019 December 1997 Insp Repts 50-413/97-14 & 50-414/97-14 on 971012-1122. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20199G0351997-11-10010 November 1997 Notice of Violation from Insp on 970831-1011.Violations Noted:Licensee Failed to Follow Procedures for Security Badge Access Control as Evidenced.On 970909,security Failed to Destroy & Unassign Access Badge of Terminated Individual IR 05000413/19970121997-11-10010 November 1997 Insp Repts 50-413/97-12 & 50-414/97-12 on 970831-1011. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support as Well as Results of Announced Inspection by Regional Security Inspector ML20211L3051997-09-26026 September 1997 Notice of Violation from Insp on 970720-0830.Violation Noted:On 970727,technician Failed to Correctly Review Drawing Number CNEE-2792-01.02,connection Diagram,Main Steam Sys Terminal Cabinet 2SMTC1,rev 12 IR 05000413/19970111997-09-26026 September 1997 Insp Repts 50-413/97-11 & 50-414/97-11 on 970720-0830. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000413/19970101997-09-11011 September 1997 Insp Repts 50-413/97-10 & 50-414/97-10 on 970623-0731.No Violations Noted.Major Areas Inspected:Licensee Calculations,Analysis & Other Engineering Documents ML20210N7341997-08-18018 August 1997 Insp Repts 50-413/97-09 & 50-414/97-09 on 970608-0719. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support ML20210N7111997-08-18018 August 1997 Notice of Violation from Insp on 970608-0719.Violation Noted:On 970424,operations Test Group Technician Failed to Open Valve 2NV-873 as Required by Step 2.2.3 of PT/2/A/4200/01C,resulting in Closed Test Vent Flowpath 1999-09-30
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Inspection Report - Catawba - 1999010 |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket Nos: 50-413, 50-414 License Nos: NPF-35, NPF-52
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Report Nos.: 50-413/99-10,50-414/99-10 Licensee: Duke Energy Corporation System: Catawba Nuclear Station, Units 1 and 2 Location: 422 South Church Street Charlotte, NC 28242 Dates: March 14 through April 24,1999 Inspectors: D. Roberts, Senior Resident inspector R. Franovich, Resident inspector Approved by: C. Ogle, Chief Reactor Projects Branch 1 Division of Reactor Projects
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Enclosure
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9905250204 990510 PDR ADOCK 05000413 G PDR
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EXECUTIVE SUMMARY Catawba Nuclear Station, Units 1 and 2 NRC Inspection Report 50-413/99-10,50-414/99-10 This specialinspection focused on the integrated efforts of the Catawba Nuclear Station staff to evaluate, determine the root cause of, and correct a licensee-identified configuration control problem affecting the Standby Shutdown System from December 16 through 29,1998. The report covers the resident inspection period from March 14 to April 24,1999. [ Applicable template codes and the assessment for items inspected are provided below.)
Operations
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An apparent violation of previous Technical Specification 3.7.13 [now Selected Licensee Commitment item 16.7-9 (Standby Shutdown System)] was identified concerning two mispositioned electrical circuit breakers that rendered the Standby Shutdown System inoperable from December 16 through 29,1998. This issue affected both Catawba unit (Section 02.1; [1 A - eel])
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Upon discovery of the mispositioned breakers, licensee personnel promptly restored the Standby Shutdown System to operable status and made appropriate notifications to the NRC in the time period required. (Section O2.1; [1 A, 5A - POS])
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The licensee's procedures for operating the Standby Shutdown System during certain flood, power, fire, and security events were adequate to maintain equipment protection and perform their intended functions. Only minor enhancements were neede Licensee personnel interviewed were knowledgeable of these procedures and how to implement them. (Section O3.1; [1C,38 - POS))
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The licensee's root cause evaluation provided in Licensee Event Report (LER) i 50-413/98-19 sufficiently developed human performance issues that resulted in the j mispositioned Standby Shutdown System breakers. The licensee adequately addressed possible contributing factors in its corrective action program. (Section 08.1; [5B - POS])
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.c Report Details Summary of Plant Status During the period of this event (December 16 through 29,1998) both units were at approximately 100 percent reactor powe . Operations 02 Operational Status of Facilities and Equipment O2.1 Standby Shutdown SystemlSSS) Inocerable Due to Personnel Error Durina Eauipment Restoration Process Inspection Scope (71707)
The inspectors reviewed the circumstances associated with LER 50413/98-19 (previously discussed in inspection Report 50-413,414/98-12), in which the SSS was determined to be inoperable for nearly two weeks because two circuit breakers in a SSS motor control center were misaligned. The inspectors discussed this issue with plant personnel, reviewed SSS operating and test procedures, reviewed the restoration procedure associated with SSS maintenance activities on December 16,1998, and reviewed the licensee's immediate corrective actions for restoring system operabilit Observations and Findinas On December 29,1998, the licensee discovered that two breakers associated with the SSS were open when they should have been closed. The breakers were F02C, Motor Control Center 1EMXS Attemate Supply, and R03D, Motor Control Center 2EMXS Alternate Supply. With the two breakers open, the SSS was inoperable for Units 1 and 2. The licensee determined that the two breakers had been in the incorrect position for 13 days, which exceeded the allowed outage time of seven days before action to initiate a unit shutdown to Mode 3 (hot standby) was required within the following six hour SSS Backaround information The SSS is a non-safety-related system that is used to cope with certain flood, power, fire, and security events in order to achieve and maintain hot standby condition for one or both units. The SSS is utilized for certain events that may result in the loss of normal reactor coolant pump (RCP) seal injection. This involves a time-critical task to provide sealinjection with the associated unit's standby makeup pump (which can be powered from 1SLXG using the SSS diesel) within 10 minutes in order to maintain RCP seal integrity. Some of the SSS loads are supplied from 1(2)EMXS, which is normally aligned to the A train 4160 volt alternating current (VAC) vital electrical bus. Procedure OP/0/B/6100/013, Standby Shutdown System Operations, Revision 41, directs operators to open breaker 1(2) F01 A associated with 1(2)EMXA, which is powered from 1(2) ETA (the A train 4160 VAC vital bus), and close breaker 1(2)F03A associated with 1SLXG, the auxiliary power supply, during postulated events. If power to 1SLXG is lost, the SSS diesel engine will be manually started to power the SSS loads, assuming the required breaker alignment is in place. The standby makeup pump suction and discharge isolation valves are powered from 1(2)EMXS. These valves are normally closed and would not be capable of opening and providing RCP sealinjection with breakers F02C and R03D open since they are in series with breaker 1(2)F03A, respectivel .,
To ensure that the time-critical task of providing RCP seal injection can be performed within 10 minutes, the licensee has procedurally minimized the number of breakers that need to be manipulated (only F01 A and F03A) to transfer power to 1SLXG. With no procedural steps provided to verify that the third breaker (F02C for Unit 1 and R03D for Unit 2) was closed, the ability to provide reactor coolant pump seal injection within 10 l minutes could not be ensure Personnel Error Durino Eouioment Restoration Procedure Devetooment The licensee determined that breakers F02C and R03D had been left in the open position following preventive maintenance on December 16,1998. The normally closed breakers were tagged and placed in the OFF (open) position in support of the maintenance. Following completion of the maintenance activities, the tags were removed from the breakers, but the breakers were left in the OFF position in accordance with the system restoration procedure, Tag-Out 08-2811. The system restoration procedure incorrectly specified that the breakers be restored in the open position. The licensee determined that a senior reactor operator (SRO) who generated the restoration procedure assumed that, since the breaker was associated with an alternate power supply, then the normal position of the breaker was OFF. This SRO failed to reference applicable procedures to verify the normal breaker position. A second SRO reviewed and approved the tag-out procedure and missed the error. The misaligned breakers were identified and questioned by another operator on December 29,1998, who was performing an unrelated procedure validation walk-throug Operation Management Procedure (OMP) 2-18, Tagout Removal and Restoration Procedure, Revision 50, Step 6.2, Restoration / Partial Restore Record Sheet, item AA, states that equipment is to be normally returned to the position specified by a governing operating procedure checklist, the body of a goveming procedure, or as specified by the approving SRO based on plant conditions. The i.ispectors determined that the governing operating checklists for the two SSS breakers were not reviewed when the operators determined the required restored positions. Discussions with licensee personnel and review of assot nd Problem Investigation Process report (PIP)
O-C98-4935, revealed that othen possible contributing factors included the fact that the restoration procedure did not reference OP/1/A/6350/001, Normal Power Checklist, which specifies the normal operating positions of the breakers; and station drawings did not accurately depict the breakers' normal operating positions. The inspectors concluded that these contributors did not cause the human performance error when the clearance restoration procedure was being developed and approved by the SROs in support of the December 16,1998, maintenance activities. These items were, however, properly included in the licensee's corrective action progra Root Cause Determination The licensee determined that the root cause for this event was inadequate work practices. Operations personnel failed to follow the established practice of reviewing OP/1/A/6350/001, Normal Power Checklist, to determine the correct normal (restored)
position of breakers F02C and R03D. Based on the breakers' labels, operations personnel wrongly assumed that the normal position of the breakers was open. The inspectors concluded that the licensee's root cause determination, as well as its development of possible contributing factors in the corrective action program, was
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comprehensive. Several short- and long-term corrective actions were specified to restore operability and prevent recurrence. These included specifying, in the equipment data base and locally at the breakers, that having them in the OFF (open) position would render the SSS inoperable. Other actions were taken to address the human performance issue Safety Sianificance
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The SSS is not considered safety-related. However, the SSS provides an alternate and independent means for maintaining the plant in a safe shutdown (for the SSS this is Hot .
Standby [ Mode 3]) condition following certain loss of power, flooding, fire, and security events that result in the loss of normal RCP seal injection. These events are not ,
assumed to be concurrent with a design basis accident. Safe shutdown is achieved when: (1) the reactor is prevented from achieving criticality; and (2) adequate heat sink is provided to ensure reactor coolant system pressure and temperature design and safety limits are not exceeded. Upon a loss of normal RCP sealinjection, the SSS is placed in service and the associated unit's standby makeup pump is started to provide seal injection. This is to be accomplished within 10 minutes to ensure that significant RCP seal damage and a resultant small break loss of coolant accident do not occu With breakers F02C and R03D in the wrong positions and not referenced in the SSS operating procedure, the SSS's ability to perform its intended safety function of maintaining RCP seal integrity could not be ensure Reculatory Sianificance The inspectors concluded that the SSS was inoperable from December 16 through 29, 1998, without appropriate actions being taken to restore operability within seven days or perform a plant shutdown within the following six hours as required by Technical Specifications (TS). [As of January 16,1999, following the licensee's conversion to improved TS, this requirement was transferred to the Selected Licensee Commitments (SLC) document (item 16.7-9), considered Chapter 16 of the Catawba Updated Final Safety Analysis Report.) The licensee's failure to restore SSS operabiity or perform a plant shutdown within allowed outage times is considered an apparent violation of previous TS 3.7.13. This is identified as apparent violation (eel) 50-413,414/99-10-01:
Standby Shutdown System Inoperable in Excess of TS Limits Due to Mispositioned Circuit Breaker c. Conclusions An apparent violation of previous Technical Specification 3.7.13 [now Selected Licensee Commitment item 16.7-9 (Standby Shutdown System)) was identified concerning two mispositioned electrical circuit breakers that rendered the Standby Shutdown System inoperable from December 16 through 29,1998. This issue affected both Catawba unit Upon discovery of the mispositioned breakers, licensee personnel promptly restored the Standby Shutdown System to operable status and made appropriate notifications to the NRC in the time period require j J
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03 Operations Procedures and Documentation O3.1 SSS Operatina Procedures and Plant Staff Knowledae - General Comments (71707)
The inspectors reviewed procedures associated with the operation of the SSS for loss of nuclear service water, loss of component cooling water, and station blackout events (i.e., events resulting in loss of normal RCP seal injection), and interviewed operations and security personnel responsible for implementation. One minor discrepancy was identified in OP/0/B/6100/013, Standby Shutdown System Operations, Revision 4 Procedural steps goveming the transfer to the SSS referenced a wrong structural
' column identification number in describing a critical terminal box location. This item was communicated to station personnel for correctio Otherwise, the licensee's procedures for operating the SSS during certain flood, power,
. fire, and security events were adequate to maintain equipment protection and perform their intended functions. Licensee personnel interviewed were knowledgeable of these procedures and how to implement the Miscellaneous Operations issues (40500, 92901)
- 08.1 - (Closed) LER 50-413/98-19-00: Standby Shutdown System inoperable in Excess of Technical Specification Allowed Outage Time due to Mispositioned Breakers Caused by Personnel Error The licensee's root cause evaluation provided in this LER sufficiently developed human -
performance issues that resulted in the mispositioned breakers. The licensee adequately addressed possible contributing factors in its corrective action progra Based on the inspectors' review of the subject event, as described in Sections 02 and
' 03 of this inspection report, this LER is close V. Management Meetmgs X1 Exit Meeting Summary The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on May 3,1999. The licensee acknowledged the findings presented. No proprietary information was identife .
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PARTIAL LIST OF PERSONS CONTACTED Licensee R. Beagles, Safety Assurance Manager M. Boyle, Radiation Protection Manager S. Bradshaw, Safety Assurance Manager G. Gilbert, Regulatory Compliance Manager *
R. Glover, Operations Superintendent P. Herran, Engineering Manager R. Jones, Station Manager G. Peterson, Catawba Site Vice-President F. Smith, Chemistry Manager R. Parker, Maintenance Manager INSPECTION PROCEDURES USED IP 40500: Effectiveness of Licensee Controls in identifying, Resolving, and Preventing Problems IP 71707: Plant Operations IP 92901: Followup - Operations ITEMS OPENED, CLOSED, AND DISCUSSED Opened 50-413,414/99-10-01 eel Standby Shutdown System inoperable in Excess of TS Liro;ts Due to Mispositioned Circuit Breakers (Secuon O2.1)
Qloped 50-413/98-19-00 LER Standby Shutdown System inoperable in Excess of Technical Specification Allowed Outage Time due to Mispositioned Breakers Caused by Personnel Error (Section 08.1)
LIST OF ACRONYMS USED CFR - - Code of Federal Regulations eel -
Escalated Enforcement item (Apparent Violation)
LER -
Licensee Event Report NRC -
Nuclear Regulatory Commission PIP - Problem Investigation Process RCP -
Reactor Coolant Pump SLC -
Selected Licensee Commitments SRO -
Senior Reactor Operator SSS -
Standby Shutdown System TS- -
Technical Specification ,
VAC - Volts Attemating Current
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