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| | number = ML20234E507 | | | number = ML20205B791 |
| | issue date = 07/02/1987 | | | issue date = 03/13/1987 |
| | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/86-28.Ack That Rev 3 to Procedure UNT-5-004 May Be Limited in Scope to Installed Equipment & Not Specifically Violated | | | title = Insp Rept 50-382/86-28 on 861117-21.Violation Noted:Failure to Comply W/Procedures for Control of Temporary Alterations |
| | author name = Gagliardo J | | | author name = Boardman J, Hunnicutt D |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = Dewease J | | | addressee name = |
| | addressee affiliation = LOUISIANA POWER & LIGHT CO. | | | addressee affiliation = |
| | docket = 05000382 | | | docket = 05000382 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = NUDOCS 8707070593 | | | document report number = 50-382-86-28, NUDOCS 8703300044 |
| | title reference date = 04-16-1987 | | | package number = ML20205B729 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS |
| | page count = 2 | | | page count = 12 |
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| . 9 3 In Reply Refer To:
| | APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION |
| Docket: 50-382/86-28 M gg Louisiana Power & Light Company ATTN: J. G. Dewease, Senior Vice President Nuclear Operations N-80 317 Baronne Street New Orleans, Louisiana 70160 Gentlemen:
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| Thank you for your letter of April 16, 1987, in response to our letter I and Notice of Violation dated March 17, 198 We have reviewed your reply and !
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| find it responsive to the concerns raised in our Notice of Violation. We acknowledge that your Procedure UNT-5-004, Revision 3, may be limited in scope
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| to installed equipment and therefore was not specifically violated; however, 1
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| the failure of your Procedure ME-7-002, Revision 5 to assure proper restoration of equipment following a bench test is still in violation of the requirements of 10 CFR 50, Appendix B, Criterion V to provide documented procedures of a type appropriate to the circumstance We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine
| | ==REGION IV== |
| | NRC Inspection Report: 50-382/86-28 License: NPF-38 Docket: 50-382 Licensee: Louisiana Power & Light Company (LP&L) |
| | N-80 317 Baronne Street New Orleans, Louisiana 70160 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection Conducted: November 17-21, 1986 Inspector: kN 3//3/F7 |
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| | John Boardman, Reactor Inspector Operations Da'te Section, Reactor Safety Branch Accompanied by: Howard Stromberg, EG&G , |
| | Clarke Kido, EG&G Approved By: h/ |
| | D. M. Hunnicutt, Chief, Operations Section 3//3/F7 Date ' |
| | Reactor Safety Branch Inspection Summary: |
| | Inspection Conducted November 17-21, 1986 (Report 50-382/86-28) |
| | Areas Inspected: A Region IV team inspection of licensee maintenance activities was performed. The inspection covered maintenance program implementation, maintenance program, instrument and control maintenance, and electrical maintenanc Results: Of the four areas inspected, one violation was identified (failure to comply with procedures for control of temporary alterations). |
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| Sincerely,
| | %33$$ock |
| .Dricinal Signed by:
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| R.E.HALU J. E. Gagliardo, Chief Reactor Projects Branch cc:
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| Louisiana Power & Light Company ATTN: G. E. Wuller, Onsite Licensing Coordinator P. O. Box B Killona, Louisiana 70066 RIV:RSB/0S y)Y OS gg RSB
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| /N RPB JRBoardman:gt DMHunnicutt TFWesterman gJEGagliardo 7 / 1 /87 ]/)/87 1/t/87 7/(/87
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| ?Dk 3 670702 F l0$[K 05000382PDR I | |
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| | DETAILS Persons Contacted |
| | *J. Dewease, Senior Vice President, Nuclear Operations |
| | *R. P. Barkhurst, Vice President, Nuclear Operations |
| | *K. L. Brewster, Lic. Eng., Operational Licensing |
| | *N. S. Carns, Plant Manager |
| | *K. W. Cook, Nuclear Safety & Regulatory Affairs Manager |
| | *C R. Gains, Operations Interface |
| | *T. F. Gerrets, Nuclear QA Manager |
| | *J. R. McGaha, 0&M Assistant Plant Manager |
| | *F. J. Engle Bracht, Nuclear Administrative Services Manager |
| | *S. A. Alleman, Assistant Plant Manager, Technical Services |
| | *T. H. Smith, Maintenance Superintendent |
| | *A. S. Lockhart, Nuclear Operational Safety Analysis Manager |
| | *K. L. Brewster, Licensing Engineer - Operational Licensing T. Moore, Electrical Supervisor T. Smith, Maintenance Superintendent B. Thigpen, Mechanical Maintenance Assistant Superintendent J. Begnaud, Mechanical Supervisor, Nuclear L. Lehmann, Mechanical Supervisor, Nuclear The NRC inspector also interviewed additional licensee and contractor personnel during the inspectio * Denotes those attending the exit interview on November 21, 198 The senior resident inspector attended the exit intervie . Actions on Previous Findings (Closed) Unresolved Item (50-382/8504-02) Closure of Ebasco purchase orders. For the orders included in the inspector's sample, licensee personnel provided documentation of closure satisfying the NRC inspector that no significant problem appears to exist in this are . Temporary Alteration Control During the inspection, the NRC inspector reviewed the following procedures provided by licensee personnel: |
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| | UNT-5-004, Revision 3, Administrative Procedure Temporary Alteration Control |
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| | ME-7-002, Revision 5. Maintenance Procedure Molded-Case Circuit Breakers and Thermal Overload Relays |
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| | UNT-5-004, Revision 3. Section 3.1 defines a temporary alternation as any short tem addition to, removal from or change in the function of a system or any of its components which is not in accordance with approved-Waterford III desig Specific controls are required by UNT-5-004, Revision 3. for temporary alterations, unless prescribed controls are contained in procedures which perform temporary alteration ME-7-002, Revision 5. specifies and defines performance testing of molded-case circuit breakers. Certain tests, such as the instantaneous trip test, Section 8.5, specify removal of current-limiting fuses and their replacement with shorting devices for the performance of the tes No note, or procedure step, specifies or requires, the removal of the shorting devices, and replacement of the fuses required for breaker operability after completion of testin Procedure ME-7-002, Revision 5, does not reference procedure UNT-5-00 ' Licensee personnel indicated that temporary replacement of fuses with shorting bars, particularly for shop testing, had not been considered to be a temporary modificatio Failure to comply with UNT-5-004, Revision 3, Sections 4.0 and 5.0, and subsections thereto, in the removal and replacement of fuses for testing of circuit breakers is an apparent violation of 10 CFR Part 50, Appendix B, Criterion V, and ANSI N18.7-1976, Section 5. (382/8628-01) Maintenance Program The NRC inspector reviewed the licensee's maintenance progra Appropriate personnel in management, supervision, and crafts were interviewed concerning their areas of responsibility and their understanding of the applicable procedure The plant was preparing for its first refueling outage when the inspection was conducted. Certain corrective and many preventive maintenance actions had been rescheduled to be accomplished during the outage. Various training classes had been held to prepare personnel for work on components such as valves, pumps, snubbers, and energency diesel generator Personnel were temporarily reassigned to handle responsibilities in maintenance planning and scheduling, plant engineering, and maintenance trainin . . |
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| | Based on interviews with maintenance personnel and observation of Condition Identifications Work Authorization (CIWAs) 28583, 29923, and 23768 it appeared to the NRC inspector that the licensee relies heavily upon worker experience and verbal communication in the performance of maintenanc Maintenance procedures required careful interpretation and were usually augmented by the worker's personal experience or detailed instructions from the most cognizant supervisor. A concern of the NRC inspector was that some procedures as written may be too vague for a worker |
| ,-.- | | ; with limited experience to properly perform the task. It appeared that procedural corrections and clarifications considered necessary by maintenance personnel were not being routed to the planner so that the procedures could be amended, as appropriat This concern was discussed with the licensee, who indicated that a reorganization is scheduled shortly to more closely integrate personnel and responsibilities. In implementation of this concept, the snubber maintenance program is undergoing review by plant engineering, maintenance planning, and mechanical maintenanc The NRC inspector reviewed three maintenance activities (CIWAs 28583, 29923, and 23768). The CIWAs were reviewed to determine craft compliance with maintenance procedures, adequacy of maintenance procedures, and if required procedures and materials were present during work performanc Two completed corrective maintenance and three preventive maintenance CIWAs were reviewe In addition, the maintenance history files for the essential chillers were reviewed to determine if previous Freon leaks had occurred. No concerns were identified. The following mechanical maintenance tasks were reviewed: CIWA 25630, boric acid makeup tank pump discharge drain valve seat leak repair, CIWA 27322, essential chiller B temperature controller Freon leak repai PM Task Carri MWORFRAB2, essential chiller WC1AB refrigerant filter changeou PM Task Card MWORFRAB2, essential chiller WCIAB compressor oil and filter changeou EQ Task Card MW0EFWP02, emergency feedwater pump AB (Terry Turbine) |
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| | oil system inspect, clean, and change filter Two additional concerns were identified during this review of the maintenance progra The first was that a plant wide trending analysis program did not appear to be implemented. The second concern was that there did not appear to be a procedure being used that ensured consistency in the documents transferred to storage. In a number of packages (see Sections 4 and 5 below) there were sections that did not appear to be completed as required, and at times it could not be verified if all |
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| Louisiana Power & Light Company ATTN: N. S. Carns, Plant Manager P. O. Box B 1 Killona, Louisiana 70066 1
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| . Middle South Services ATTN: Mr. R. T. Lally l P. O. Box 61000 ! '
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| New Orleans, Louisiana 70161 Louisiana Power & Light Company ATTN: K. W. Cook, Nuclear Safety and Regulatory Affairs Manager 317 Baronne Street P. O. Box 60340 ;
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| Louisiana Radiation Control Program Director I i
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| bec to DMB (IE01)
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| *RPB *D. Weiss, RM/ALF i
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| *RRI R. D. Martin, RA i
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| *SectionChief(RPB/A) DRSP RPSB *RSB
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| * MIS System * Project Inspector, RPB
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| *RSTS Operator *R. Hall
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| *RIV File NRR Project Manager
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| | applicable documents were in the stored document files. This will remain an open item (382/8628-02) pending further review during a subsequent inspectio . Maintenance Program Implementation The NRC inspector obtained a list of maintenance activities which were scheduled for the week of November 17-21, 1986. He selected three for inspection to determine compliance with the regulations and the Waterford 3 Administrative Procedure The three maintenance activities were detailed on Condition Identification and Work Authorization (CIWAs) for the following corrective maintenance: |
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| | troubleshoot Freon leak found at electrical box on the compressor to Essential Chiller AB, troubleshoot RCS leakage past seals on Charging Pump B, and preventive maintenance of type PSA-3 mechanical snubber The CIWAs were identified as CIWA 28583, 29923, and 23768, respectivel Each CIWA was reviewed for authorizing signatures, spare parts control, inspection adequacy, mechanical qualification, adequacy of maintenance performed and post-maintenance functional testing and restoration. The CIWA's were also reviewed to determine compliance with the requirements of the following procedures: |
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| LO UlSI POWE R & AN L1GHTA / 317 NEWBARONNE
| | MM-1-002, Revision 2, " Mechanical Maintenance Practice," dated August 24, 198 MD-1-007, Revision 2, " Preventive Maintenance Task Identification," |
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| | dated November 15, 198 " |
| STREET ORLEANS, LOUISlANA P. O BOX 60340 70160 * (504) 595 3100 U1'sl$ES SE April 16, 1987 ?
| | MD-1-004, Revision 6, " Preventive Maintenance Scheduling," dated May 21, 198 * |
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| | UNT-5-002, Revision 5, " Administrative Procedure, Condition Identification and Work Authorization (CIWA)," dated January 13, 198 * |
| W3P87-1010 A4.05 QA
| | MD-1-011, Revision 3, Maintenance Procedure Development, Review, Approval, Change, Revision, Deletion MD-1-014, Revision 1, " Administrative Procedure, Conduct of Maintenance," dated November 21, 198 MM-6-023, Revision 1, " Mechanical Snubber (Shock Arresters) |
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| | Maintent.nce," dated October 21, 198 . |
| ' % Fu; . l U.S. Nuclear Regulatory Commission L M \~- '':p!":I }li ATTN: Document Control Desk ;j
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| ll Washington, D.C. 20555 ~
| | MM-7-011, Revision 3, " Mechanical Snubber Test," dated November 14, 198 The troubleshooting of the Essential Chiller AB Freon leak was witnessed by the NRC inspector. The NRC inspector reviewed the job from receipt of the CIWA by the maintenance mechanic, through the mechanic's disassembly and inspection of the pump out compressor, his written work order instructing the planner to contact the vendor for detailed information and replacement parts, the planner's purchase order for the spare parts, and the maintenance supervisor's commitment to reassemble and test the chille Upon disassembly of the electrical box on the pump out compressor, the mechanics found that an unused electrical connection had been improperly sealed with a fibrous plug, and a cardboard and plastic spacer. A telephone call to the compressor manufacturer indicated that a double locking nut connection should have been made. The licensee amended the CIWA to plug the connection as specified by the manufacturer. The licensee intended to correct only Chiller AB, although there are two other identical chillers at the plant. |
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| g 2 l jgp i r i L i Subject: Waterford 3 SES I Docket No. 50-382
| | , The NRC inspector had two concerns relating to this maintenance work. The first concern was that the technical manual for the pump-out compressor lacked sufficient detail to describe the correct electrical connection When the licensee started work, he determined that the technical manual did not provide sufficient detail to allow repairs to be made. When disassembly was completed, the manufacturer was called ar.d his advice was followed to make repairs. These licensee actions adequately addressed this concer A second concern was that the licensee did not intend to inspect the other two essential chillers unless a similar Freon leak occurred, at which time the licensee would follow the same corrective action. The licensee was asked to confirm that the unused electrical connections for each essential chiller pump out compressor has been properly plugged and ensure that preventive measures are in place to prevent recurrence of the Freon leak problem. The licensee's actions had no significant effect on safety. The components were safety-related. The licensee was not correcting a known common mode failure mechanism that affected 2 of 3 safety system The troubleshooting of a charging pump seal leak was followed by the NRC inspector. The NRC inspector witnessed the job from receipt of the CIWA by the mechanic, through the obtaining of spare parts, verification of the status of equipment tagged out, and clearance for access to the vital are The NRC inspector discontinued observations during seal replacement and functional testing because of work area health physics requirement The licensee determined that the root cause of the seal failure was deficient packing. No concerns were identifie _ _ _ _ - _ _ _ . _ . _ _ _ _ _ . _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ |
| , License No. NPF-38 NRC Inspection Report 86-28
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| Attached is the Louisiana Power and Light Company (LP&L) y,esponse to Violation No. 8628-01 identified in Inspection Report No. 86-2 If you have any questions on the response, please contact G.E. Wuller, Operational Licensing, at (504) 464-349 l l
| | The NRC inspector followed preventive maintenance of Type PSA-3 mechanical snubbers that was in progress. Licensee personnel used procedure MM-6-023, Revision 1. During work, the NRC inspector observed that several steps in MM-6-023 were not followed (for example, step:. 8.2.1.10, .11, and .12), |
| l Very truly yours, C
| | since they applied only to a major overhaul of the snubber. Prior approval to omit the steps had not been documented, or authorized by the maintenance supervisor. The mechanic's work was based on procedure MM-6-023, in general, plus " hands-on" experience gained from a snubber workshop held at the vendor's factory. Revision 1 of procedure MM-6-023 was verified to be the latest revision controlled by the document records departmen Discussions with the mechanic, supervisor, and planner indicated that the snubber procedure would be revised in the near futur The NRC inspector noted a weakness dealing with the administrative aspects of the above maintenance. As stated in the previous paragraphs, the mechanics did not perform several steps that the craftsmen knew or believed, were optional. This practice can result in an error and maintenance which is not approved. The NRC inspector's concern was that a junior mechanic was undergoing on-the-job training by a senior mechanic who did not follow the maintenance procedure as written. The licensee was asked to review procedures MM-6-023 and MM-7-11 and ensure that the appropriate steps are identified for performance of all levels of maintenance specified by these procedures. This review will ensure compliance with step 14 of Attachment 6.10 to Procedure MD-1-011, which indicates that an optional step in a maintenance procedure shall be clearly identified as suc . Licensee Instrumentation Maintenance Program The NRC inspector performed an inspection of the maintenance program in the instrument and control areas in accordance with Inspection and Enforcement Manual Section 62704 and the Waterford 3 Administrative Procedures. Maintenance history, calibration records, procedures, work item tracking forms, and maintenance work request forms were obtained and reviewed. Selected instrument and control supervisors and technicians of the I&C Maintenance Organization were interviewed to determine their areas of responsibilities, functions, and qualification Two work activities in progress were witnessed by the NRC inspector to determine if the technicians were following appropriate maintenance procedures. The two activities were: (1) MI-5-160, Revision 1, Calibration of Plant Protection System Test and Calibration Card and Digital Volt Meter (DVM), and (2) MI-3-350, Revision 5, Containment Purge Isolation Area Radiation Monitor Channel "A" or "B" Functional Test ARM-IR-5024S 50255, 5027 There were a number of discrepancies noted during the performance of these activitie The following are examples of procedures not being followed: Step 8.4 of MI-5-160 (Calibration of Plant Protection System Test and Calibration Card and DVM) indicated that the DVM should be turned on and set to Volt Direct Current (VDC) Auto with the "As Found" block to be filled in on Attachment 10.1. The technicians performing the |
| oY l A h K.W. Cook Nuclear Safety and Regulatory Affairs Manager T( y s
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| \ cu cc: R.D. Martin, NRC Region IV s G.W. Knighton, NRC-NRR J.H. Wilson, NRC-NRR V'
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| | calibration understood this step to mean the test instrument and not the DVM being calibrated. An entry was not made in Attachment 1 for the DVM. The actions were not consistent with the procedure. It should be noted that the instruction was misleadingly vague, since it appeared to be applicable to the test instrument instead of the DVM which is constantly energized and does not have an " Auto" positio Step 8.28 of MI-5-160 required that a calibration sticker be attached to the DV Instead it was attached to the panel above the DV Step 8.1.1 of MI-3-350 (Containment Purge Isolation Area Radiation Monitor Channel "A" or "B" Functional Test (ARM-IR-5027S)) required a jumper to be used when the Containment Purge Isolation Valves are shut. Discussions with the technicians indicated that the jumper installation was not always performed. Operations personnel dictated jumper installation and decided whether or not a potential existed for the valves to be operated before testing was completed. The procedure does not allow this choice. |
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| | The second item found during work observations was that the procedures were in error in a number of step The following are examples where errors were noted: Step 8.19 of MI-5-160 indicated that both " Bistable Select" switches should be verified in the "Of f" position. Only one has an off position; the other has a line indicating of Step 8.20 of MI-5-160 indicated that the " Input Select" switch was to be set to " Input." The switch was not removed from or verified in the " Input" position at the start of the procedure. It is possible that the switch should have been verified in the " Input" position at the start of the procedure in order to ensure correct voltages, Step 8.3.4 of MI-3-350 indicated that the health physics technician was to be informed that the monitor was back in service. The procedure, however, does not require the health physics technician to be informed when it was removed from service. This was an omission from this procedure. The technician indicated that most of the other procedures had this requirement correctly identified. It should be noted that the I&C technician informed the health physics technician when the instrument was removed from service for testing, however, it was done as a normal practic The third item identified during work observations was that the procedures permitted specific or " equivalent" instruments to be used for performing a procedure. However, the licensee had not identified which instruments are equivalent to each other; nor was the basis for equivalency verified before testing was performed. This policy does not assure that instrument sensitivity requirements will be me _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - |
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| | Examples found by the NRC inspector where one instrument was identified and another used were as follows: Procedure MI-5-160, Revision 1, Step 6.0, indicated a Fluke 8500A DVM was to be used. Instead, a health physics (HP) instrument was use Procedure MI-3-350, Step 6.0, indicated a Fluke 8600A Digital Multimeter was to be used. Instead, an HP instrument was use Documentation associated with ten completed maintenance activities was obtained and reviewed. The ten activities were: CIWA 028825, nitrogen pump level switch NG-ILS-3006 out of calibratio CIWA 025448, component cooling water to dry tower isolation valve low air pressure switch CC-IPS-3085B mounting repair CIWA 029024, charging pump AB spurious low suction pressure trip switch (CVC-MPMP0001AB) troubleshootin CIWA 025719, steam generator No. 1 pressure transmitter SG-IPT-1013A erratic output troubleshooting, CIWA 025913, boric acid condensate tank "B" level controller (BM-ILIC-0626) repai CIWA 022177, annunciator LO705 troubleshooting and repai CIWA 006276, SUPS IAB blown fuse F42 replacemen CIWA 023828, chill water pressure transmitter CHW-IPT-5011BS leaking vent plug replacement, CIWA 025452, containment spray flow transmitter CS-IFT-7122AS high flow indicatio CIWA 028099, boric acid condensate tank "B" level controller (BM-ILIC-0626) maintenanc The review of these completed items identified three areas of apparent weakness as follows: |
| | The first area was a concern related to not identifying equivalent instruments. CIWA (Condition Identification Work Authorization) |
| | 028825 (item a. above) identifies a 0-415 inches water column (INWC) |
| | instrument to be used for calibration where an 0-830 INWC was use As stated previously, this does not ensure that necessary instrument sensitivities are me Another example was seen in CIWA-025448 (item b. above) where a 0-100 psi Heise test gauge and Fluke 8600A |
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| | DVM were identified for use as test equipment. Instead of using the identified equipment, a Helicoid 0-100 psi gauge and a Triplet meter were use * |
| | The second weakness identified during review by the NRC inspector was that there appeared to be inconsistencies in the document review process. In CIWA 025719 (item d. above) Section D (corrective maintenance control section) was not filled out. CIWA 025913 (item e. above) identified one of the test instruments by manufacturer's name and not by its control numbe This does not permit easy traceabilit * |
| | A third weakness was incomplete reviews as identified in CIWA 022177 (item f. above). On CIWA 022177, addendum page 11, it was indicated that plant engineering was to evaluate the acceptability of the switches used for initiating the alarm. It was not apparent that the review had been performed. No other weaknesses were noted during the |
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| | review of these maintenance documents. These concerns will be an open item (382/8628-03) to be reviewed generically during a subsequent inspectio . Licensee Electrical Maintenance Program The NRC inspector performed an inspection of the Maintenance Program in the electrical area. Maintenance history, work item tracking forms, maintenance work requests, qualification records, document control procedures, and replacement part control records were obtained and reviewed. Selected Electrical Maintenance Organization personnel (electrical supervisors and electricians) were interviewed to determine their areas of responsibilities, functions, and qualification Three maintenance action items were witnessed to ensure that the electricians performin0 the maintenance tasks followed the appropriate maintenance procedures. All three items involved the testing of HPCI Pump AB relays. Testing was performed in accordance with the following procedures: |
| | ' ME-7-035, Revision 1, G.E. Auxiliary Relays, Models HGA11A through HGA11X ME-7-030, Revision 1 G.E. Auxiliary Relays Models HGA17A through HGA17T ME-7-033, Revision 1, G.E. Auxiliary Relay HGA14 The NRC inspector identified two areas of concern. The first concern involved test equipment. In maintenance procedure ME-7-035, Step 6.2.1, Doble equipment, or equivalent, was identified to be used to perform the testing. The technicians performing the job used Multiamp equipmen Equivalency was not determined. As stated previously, not determining equivalency or having an established equivalency list in advance fails to ensure that instrument sensitivities are acceptabl . _ _ _ . __-. -- |
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| | The second concern related to the adequacy of the procedures. Step 7.0 of maintenance procedure ME-7-033 indicated that the acceptance criterion was for the relay to pick up at rated powe The rated power was not included as part of the documentation but was determined by the technician from memory. This practice does not assure that the testing is acceptabl Another example was seen in Step 8.3.1.1 of ME-7-033, where terminals 1 and 7 were to be used for continuity verification when the relay was energize These terminals were connected to spare contact The procedure did not provide for checking contacts actually in use. This practice does not provide assurance that the relay will provide the protection intende No other concerns were identified during work observation j Procedures and other documentation associated with the following 11 i completed electrical maintenance activities were reviewed: CIWA 027805, wet cooling tower fan 6A breaker (ACC-EBTR-315A12MS) |
| | replacemen CIWA 027484, dry cooling tower fan 58 motor (CC-EMTR-315B-3F) lug repai CIWA 006299, diesel generator feeder breaker (EBKR-3A145) spring release interlock support repai CIWA 021284, flow transmitters CC-IF-5570AS and BS hydro-test validatio CIWA 004376, static uninterruptable power supply (SUPS) 3B-5 bypass , |
| | transformer firing board (ID-IDEN-PSM85) temporary modificatio l CIWA 004392, SUPS 3B-S Bypass transformer firing board ; |
| | (ID-IDEN-PSM85) testing, |
| | ' CIWA 005619, MCC 38213 and 38311 missing grommets (MCC-CABLE-GR0MS) |
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| | CIWA 009388, all safety related motor operated valves inspection and |
| | ' heater operation verificatio ! |
| | i CIWA 025125, reactor building purge exhaust fan E22 motor ' |
| | (HVRE-MTR-3A7AS) polarization index procedure revisio : CIWA 027249, cabinet C-24 temperature control (IC-ITC-3024) burnt wire repairs, CIWA 023669, fuel handling building flitration unit B heater |
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| | (HVFIHPL51148) troubleshooting and repair. |
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| | l 12 During the review of completed maintenance packages by the NRC inspector, one concern was identified. This involved document completion and review. |
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| LP&L Response To Violation No. 8628-01 1 VIOLATION No. 8628-01 Failure to Follow Procedures for Control of Temporary Modifications 10 CFR Part 50, Appendix B, Criterion V, requires that activities affecting quality shall be accomplished in accordance with approved procedures. ANSI N18.7-1976, to which the licensee is committed, Section 5.2.2, requires that procedures shall be followed. Licensee Procedure UNT-5-004, Revision 3, " Administrative Procedure Temporary Alteration Control,'' identifies specific requirements for the control and restoration of tcmporary modifications. This procedure specifies that procedures requiring temporary modifications shall either appropriately reference UNT-5-004, or contain the specified controls for temporary modification Contrary to the above, the NRC inspector on November 19, 1986, identified that licensee Procedure ME-7-002, Revision 5 " Maintenance Procedure Molded-Case Circuit Breakers and Thermal Relays," did not contain required
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| ,. controls for temporary removal and replacement of current limiting fuses during performance testing of the circuit breakers, nor reference UNT-5-00 .
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| This is a Severity Level IV violatio RESPONSE (1) Reason for the Violation This violation cites procedure ME-7-002, Molded Case Circuit Breakers and Thermal Relays, "for not containing required controls for temporary alterations as specified by UNT-5-004, Temporary Alteration control". Although ME-7-002. inadvertently omitted steps that would ensure proper restoration of equipment to its design operating condition, we do not feel that it viol'ated UNT-5-004. UNT-5-004 is a procedure written to control temporary alterations to existing, installed, operational plant equipment. ME-7-002 is a procedure which removes a piece of equipment and bench tests it. Temporary changes, | |
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| modifications, disassembly or reassembly of the equipment once removed from the plant is not considered a temporary alteration and should not fall under the requirements of UNT-5-004. Nonetheless, procedures controlling maintenance in these situations must be adequate to ensure complete and proper restoration of equipment; this is the area in which ME-7-002 was deficien (2) Corrective Action That Has Been Taken ME-7-002 has been revised to require removal of any shorting alocks that could have been previously installed, re-installation of fuses and independent verification of the came. The possibility that shorting devices could have been left in breakers previously tested by this procedure has also been considered. We are confident that this is not the case based on the following:
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| * '*~ Attschment to
| | In CIWAs (025125, 02749, 023669, and 006299), Section D (Corrective Maintenance Controls Section) of the first page was not completed, or was filled out incorrectl These deficiencies in themselves were not highly I significant, however, they demonstrated a weakness in the final document I |
| | review proces Three additional items were reviewed during review of the licensee's l |
| | electrical maintenance program as follows: |
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| . W3P87-1010
| | l The first item was the overcurrent testing of breakers important to safet This involved the concern that some breaker manufacturers |
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| Sheet 2 of 2 !
| | have specified that alternating current (AC) overcurrent testing be |
| . Section 8.6 (Thermal Element Time Delay Test) of ME-7-002 did , | | , |
| contain a note requiring removal of shorting devices and j re-installation of fuses. Section.8.6 is required each'tima the breaker is teste (Section 8.5, Instantaneous Trip-Test, had no such provisions, but is only required on newly installed breakers.)
| | performed only once in the lifetime of a circuit breaker, with |
| | ! subsequent testing to be done using direct current (DC). The l licensee response to their concern indicated that it was applicable to one type of circuit breaker at Waterford. The breakers in question were tested using an AC test source, filtering the output through a rectifier bank when testing the breaker. The testing |
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| . To date there have been no instances of shorting devices found in breakers removed from service for maintenanc All of the Electrical Maintenance procedures which cover circuit breaker testing (ME-3-315, ME-3-325, ME-3-327, ME-3-330, | | l |
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| ME-4-111 ME-4-131, ME-4-143, ME-4-145, ME-4-146, ME-4-155, ME-7-100) have been reviewed and no similar deficiencies were foun ,
| | l The second item was the replacement of Agastat time delay relays in emergency diesel generator sequencing circuits. The licensee was questioned about the use of qualified replacement relays. Procedures governing relay replacement were reviewed and found acceptabl * |
| (3) Corrective Action To Be Taken j No further action deemed necessary w-(4) Date When Full Compliance Will Be Achieved -
| | The third item was the meggering (high voltage insulation test) for long installed runs of cables. The licensee's current practice is to megger cables at the circuit breakers. This practice is acceptable when cable runs are short. When the cable runs are long, the voltage drop in the cable could prevent a valid test of insulation breakdown l resistance. The licensee committed to reviewing this concern. This |
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| Full compliance was achieved on April 8, 198 l
| | will remain an open item (382/8628-04) to be reviewed during a subsequent inspectio . Exit Interview l |
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| | l The NRC inspector met with the NRC senior resident inspector and the l licensee representatives identified in paragraph 1 at the conclusion of I |
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| | the inspection on November 21, 198 The NRC inspector summarized the scope and findings of the inspection. |
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Category:INSPECTION REPORT
MONTHYEARIR 05000382/19990201999-10-21021 October 1999 Insp Rept 50-382/99-20 on 990815-0925.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support Activities IR 05000382/19990141999-10-19019 October 1999 Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Major Areas Inspected:Operator Requalification Training Program IR 05000382/19990181999-09-29029 September 1999 Insp Rept 50-382/99-18 on 990830-0902.Violations Noted.Major Areas Inspected:Implementation of NRC-approved Fire Protection Program IR 05000382/19990191999-09-27027 September 1999 Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted. Major Areas Inspected:Plant Support IR 05000382/19990151999-09-14014 September 1999 Insp Rept 50-382/99-15 on 990719-23 with in Ofc Insp Until 0819.No Violations Noted.Major Areas Inspected:Assessment of 10CFR50.59 Safety Evaluation Program & Review of Previous Insp Findings Involving Tornado Missile Protection IR 05000382/19990071999-09-0808 September 1999 Insp Rept 50-382/99-07 on 990601-11.Noncited Violations Identified.Major Areas Inspected:Operations IR 05000382/19990161999-09-0101 September 1999 Insp Rept 50-382/99-16 on 990704-0814.Noncited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support IR 05000382/19990101999-08-11011 August 1999 Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Major Areas Inspected:Solid Radioactive Waste Mgt & Radioactive Matl Transportation Programs IR 05000382/19990131999-07-15015 July 1999 Insp Rept 50-382/99-13 on 990523-0703.Noncited Violations Noted.Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities IR 05000382/19990121999-06-21021 June 1999 Insp Rept 50-382/99-12 on 990524-27.No Violations Noted. Major Areas Inspected:Operational Status of Licensee Emergency Preparedness Program IR 05000382/19990111999-06-18018 June 1999 Insp Rept 50-382/99-11 on 990524-28.No Violations Noted. Major Areas Inspected:Implementation of Liquid & Gaseous Radwaste Effluent Mgt Program,Status of Effluent Radiation Monitors & Counting Room Instruments IR 05000382/19990091999-06-0303 June 1999 Insp Rept 50-382/99-09 on 990411-0522.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19990061999-05-18018 May 1999 Insp Rept 50-382/99-06 on 990405-09.Non-cited Violations Identified.Major Areas Inspected:Issue Previously Identified During Architect Engineering Insp Which Documented NRC Insp Rept 50-382/98-201 IR 05000382/19990051999-05-10010 May 1999 Insp Rept 50-382/99-05 on 990228-0410.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support ML20206F4801999-05-0303 May 1999 Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Noted & Being Considered for Escalated Eas.Major Areas Inspected:Plant Support Including Licensee Access Authorization Program IR 05000382/19990041999-04-0909 April 1999 Insp Rept 50-382/99-04 on 990301-19.One Violation Occurred & Being Treated as Noncited Violation.Major Areas Inspected: Review of Licensee Implementation of Facility ISI Program & Followup Review of Reactor Trip Breaker Performance IR 05000382/19990021999-04-0505 April 1999 Insp Rept 50-382/99-02 on 990117-0227.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support Activities IR 05000382/19990031999-03-26026 March 1999 Insp Rept 50-382/99-03 on 990308-12.Violations Noted.Major Areas Inspected:Radiation Protection Program Focusing on RF09 Refueling Outage Activities IR 05000382/19990011999-03-0303 March 1999 Partially Deleted Insp Rept 50-382/99-01 on 990125-29 & 0208-12 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Plant Support IR 05000382/19980181998-12-21021 December 1998 Insp Rept 50-382/98-18 on 981018-1128.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19980151998-11-24024 November 1998 Insp Rept 50-382/98-15 on 980906-1017.No Violations Noted. Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities IR 05000382/19980131998-11-17017 November 1998 Insp Rept 50-382/98-13 on 980831-0901 & 981005-08.No Violations Noted.Major Areas Inspected:Maint Using Guidance of Temp Instruction 2515/137, Insp of Medium-Voltage & Low-Voltage Power Circuit Breakers ML20155D0561998-10-29029 October 1998 Insp Rept 50-382/98-17 on 981005-08.Violations Noted. Major Areas Inspected:Routine Review of Radiation Protection Program Activities ML20155D5111998-10-27027 October 1998 Partially Withheld Insp Rept 50-382/98-16 on 980914-18. Violations Noted.Major Areas Inspected:Licensee Physical Security Program.Portions Withheld (Ref 10CFR2.790) ML20154L1281998-10-0909 October 1998 Insp Rept 50-382/98-14 on 980726-0905.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19980121998-08-21021 August 1998 Insp Rept 50-382/98-12 on 980614-0725.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19992011998-07-27027 July 1998 Insp Rept 50-382/99-201 on 990511-0619.No Violations Noted Major Areas Inspected:Engineering IR 05000382/19980101998-07-20020 July 1998 Insp Rept 50-382/98-10 on 980622-26.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program Including Access Authorization,Alarm Stations,Protected Area Access Control of Personnel & Packages & Vehicles IR 05000382/19980091998-07-10010 July 1998 Insp Rept 50-382/98-09 on 980503-0613.Violations Noted.Major Areas Inspected:Aspects of Operations,Maint,Engineering & Plant Support Activities.Fire Door in Reactor Auxiliary Bldg Was Observed to Be Open W/No Controls in Place IR 05000382/19980081998-05-29029 May 1998 Insp Rept 50-382/98-08 on 980322-0502.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20217B6981998-04-21021 April 1998 Insp Rept 50-382/98-06 on 980201-0321.Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000382/19980021998-03-20020 March 1998 Insp Rept 50-382/98-02 on 980202-20.No Violations Noted. Major Areas Inspected:Current Performance & Effectiveness of Corrective Action Program Including Audits & Assessments, Operations & Engineering ML20216E1461998-03-12012 March 1998 Insp Rept 50-382/98-07 on 980302-06.Violations Noted.Major Areas Inspected:Plant Support ML20216E5991998-03-12012 March 1998 Insp Rept 50-382/98-05 on 980202-12.Violations Noted.Major Areas Inspected:Licensee Physical Security Program ML20216E7621998-03-12012 March 1998 Insp Rept 50-382/97-25 on 971201-980205.Violations Noted. Major Areas Inspected:Maint & Engineering IR 05000382/19980031998-03-10010 March 1998 Insp Rept 50-382/98-03 on 980216-20.No Violations Noted. Major Areas Inspected:Operational Status of Emergency Preparedness Program ML20203L2171998-03-0303 March 1998 Insp Rept 50-382/98-04 on 980202-06.Violations Noted.Major Areas Inspected:Radiation Protection Program Including External Exposure Controls,Training Qualifications, Facilities & Equipment & Procedures & Documentation IR 05000382/19970281998-02-11011 February 1998 Insp Rept 50-382/97-28 on 971214-980131.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support Activities IR 05000382/19980011998-01-29029 January 1998 Insp Rept 50-382/98-01 on 980112-15.No Violations Noted. Major Areas Inspected:Implementation of Solid Radwaste Mgt & Radwaste/Matls Transportation Program.Quality Assurance Oversight,Training & Procedural Guidance Were Also Reviewed ML20198M2801998-01-12012 January 1998 Insp Rept 50-382/97-24 on 971102-1213.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20198C8871998-01-0505 January 1998 Insp Rept 50-382/97-26 on 971117-1205.No Violations Noted. Major Areas Inspected:Operator Activities Re Failure to Return Valve ACC-126A,auxiliary Component CWS Flow Control Valve,To Automatic Operation When Restoring CWS ML20198C4561998-01-0202 January 1998 Insp Rept 50-382/97-27 on 971117-1205.Violations Noted. Major Areas Inspected:Review of Licensee Identification That Plant Ventilation Sys Could Adversely Affect Level Indication for Refueling Water Storage Pool IR 05000382/19970181997-12-0505 December 1997 Insp Rept 50-382/97-18 on 971104-07.Violations Noted.Major Areas Inspected:Licensee Performance & Capabilities During full-scale,biennial Exercise of Emergency Plan & Implementing Procedures Performed IR 05000382/19970211997-12-0202 December 1997 Insp Rept 50-382/97-21 on 970922-26 & 1006-10.Violation Noted.Major Areas Inspected:Engineering,Maintenance & Mgt Meetings IR 05000382/19970221997-11-19019 November 1997 Insp Rept 50-382/97-22 on 970921-0001.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19970231997-11-0404 November 1997 Insp Rept 50-382/97-23 on 971006-10.No Violations Noted. Major Areas Inspected:Liquid & Gaseous Radioactive Effluent Waste Mgt Program Including Organization & Mgt Controls & Radioactive Effluent Monitoring IR 05000382/19970191997-10-24024 October 1997 Partially Withheld Insp Rept 50-382/97-19 on 970922-26 (Ref 10CFR73.21).No Violations Identified.Major Areas Inspected: Plant Support Re Land Vehicle Control Measures & Security Program IR 05000382/19970171997-10-23023 October 1997 Insp Rept 50-382/97-17 on 970929-1003.Violations Noted. Major Areas Inspected:Licensed Operator Requalification Program Following Guidelines in Insp Procedure 71001, Licensed Operator Requalification Program Evaluation IR 05000382/19970161997-10-17017 October 1997 Insp Rept 50-382/97-16 on 970810-0920.Violations Noted: Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19970201997-10-0909 October 1997 Insp Rept 50-382/97-20 on 970922-26.Violations Noted.Major Areas Inspected:External & Internal Exposure Control Programs,Surveys,Monitoring & Control of Radioactive Matl & Quality Assurance 1999-09-08
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000382/19990201999-10-21021 October 1999 Insp Rept 50-382/99-20 on 990815-0925.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support Activities IR 05000382/19990141999-10-19019 October 1999 Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Major Areas Inspected:Operator Requalification Training Program IR 05000382/19990181999-09-29029 September 1999 Insp Rept 50-382/99-18 on 990830-0902.Violations Noted.Major Areas Inspected:Implementation of NRC-approved Fire Protection Program IR 05000382/19990191999-09-27027 September 1999 Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted. Major Areas Inspected:Plant Support IR 05000382/19990151999-09-14014 September 1999 Insp Rept 50-382/99-15 on 990719-23 with in Ofc Insp Until 0819.No Violations Noted.Major Areas Inspected:Assessment of 10CFR50.59 Safety Evaluation Program & Review of Previous Insp Findings Involving Tornado Missile Protection IR 05000382/19990071999-09-0808 September 1999 Insp Rept 50-382/99-07 on 990601-11.Noncited Violations Identified.Major Areas Inspected:Operations IR 05000382/19990161999-09-0101 September 1999 Insp Rept 50-382/99-16 on 990704-0814.Noncited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support IR 05000382/19990101999-08-11011 August 1999 Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Major Areas Inspected:Solid Radioactive Waste Mgt & Radioactive Matl Transportation Programs IR 05000382/19990131999-07-15015 July 1999 Insp Rept 50-382/99-13 on 990523-0703.Noncited Violations Noted.Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities IR 05000382/19990121999-06-21021 June 1999 Insp Rept 50-382/99-12 on 990524-27.No Violations Noted. Major Areas Inspected:Operational Status of Licensee Emergency Preparedness Program IR 05000382/19990111999-06-18018 June 1999 Insp Rept 50-382/99-11 on 990524-28.No Violations Noted. Major Areas Inspected:Implementation of Liquid & Gaseous Radwaste Effluent Mgt Program,Status of Effluent Radiation Monitors & Counting Room Instruments IR 05000382/19990091999-06-0303 June 1999 Insp Rept 50-382/99-09 on 990411-0522.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19990061999-05-18018 May 1999 Insp Rept 50-382/99-06 on 990405-09.Non-cited Violations Identified.Major Areas Inspected:Issue Previously Identified During Architect Engineering Insp Which Documented NRC Insp Rept 50-382/98-201 IR 05000382/19990051999-05-10010 May 1999 Insp Rept 50-382/99-05 on 990228-0410.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support ML20206F4801999-05-0303 May 1999 Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Noted & Being Considered for Escalated Eas.Major Areas Inspected:Plant Support Including Licensee Access Authorization Program IR 05000382/19990041999-04-0909 April 1999 Insp Rept 50-382/99-04 on 990301-19.One Violation Occurred & Being Treated as Noncited Violation.Major Areas Inspected: Review of Licensee Implementation of Facility ISI Program & Followup Review of Reactor Trip Breaker Performance IR 05000382/19990021999-04-0505 April 1999 Insp Rept 50-382/99-02 on 990117-0227.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support Activities IR 05000382/19990031999-03-26026 March 1999 Insp Rept 50-382/99-03 on 990308-12.Violations Noted.Major Areas Inspected:Radiation Protection Program Focusing on RF09 Refueling Outage Activities IR 05000382/19990011999-03-0303 March 1999 Partially Deleted Insp Rept 50-382/99-01 on 990125-29 & 0208-12 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Plant Support IR 05000382/19980181998-12-21021 December 1998 Insp Rept 50-382/98-18 on 981018-1128.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19980151998-11-24024 November 1998 Insp Rept 50-382/98-15 on 980906-1017.No Violations Noted. Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities IR 05000382/19980131998-11-17017 November 1998 Insp Rept 50-382/98-13 on 980831-0901 & 981005-08.No Violations Noted.Major Areas Inspected:Maint Using Guidance of Temp Instruction 2515/137, Insp of Medium-Voltage & Low-Voltage Power Circuit Breakers ML20155D0561998-10-29029 October 1998 Insp Rept 50-382/98-17 on 981005-08.Violations Noted. Major Areas Inspected:Routine Review of Radiation Protection Program Activities ML20155D5111998-10-27027 October 1998 Partially Withheld Insp Rept 50-382/98-16 on 980914-18. Violations Noted.Major Areas Inspected:Licensee Physical Security Program.Portions Withheld (Ref 10CFR2.790) ML20154L1281998-10-0909 October 1998 Insp Rept 50-382/98-14 on 980726-0905.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19980121998-08-21021 August 1998 Insp Rept 50-382/98-12 on 980614-0725.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19992011998-07-27027 July 1998 Insp Rept 50-382/99-201 on 990511-0619.No Violations Noted Major Areas Inspected:Engineering IR 05000382/19980101998-07-20020 July 1998 Insp Rept 50-382/98-10 on 980622-26.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program Including Access Authorization,Alarm Stations,Protected Area Access Control of Personnel & Packages & Vehicles IR 05000382/19980091998-07-10010 July 1998 Insp Rept 50-382/98-09 on 980503-0613.Violations Noted.Major Areas Inspected:Aspects of Operations,Maint,Engineering & Plant Support Activities.Fire Door in Reactor Auxiliary Bldg Was Observed to Be Open W/No Controls in Place IR 05000382/19980081998-05-29029 May 1998 Insp Rept 50-382/98-08 on 980322-0502.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20217B6981998-04-21021 April 1998 Insp Rept 50-382/98-06 on 980201-0321.Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000382/19980021998-03-20020 March 1998 Insp Rept 50-382/98-02 on 980202-20.No Violations Noted. Major Areas Inspected:Current Performance & Effectiveness of Corrective Action Program Including Audits & Assessments, Operations & Engineering ML20216E1461998-03-12012 March 1998 Insp Rept 50-382/98-07 on 980302-06.Violations Noted.Major Areas Inspected:Plant Support ML20216E5991998-03-12012 March 1998 Insp Rept 50-382/98-05 on 980202-12.Violations Noted.Major Areas Inspected:Licensee Physical Security Program ML20216E7621998-03-12012 March 1998 Insp Rept 50-382/97-25 on 971201-980205.Violations Noted. Major Areas Inspected:Maint & Engineering IR 05000382/19980031998-03-10010 March 1998 Insp Rept 50-382/98-03 on 980216-20.No Violations Noted. Major Areas Inspected:Operational Status of Emergency Preparedness Program ML20203L2171998-03-0303 March 1998 Insp Rept 50-382/98-04 on 980202-06.Violations Noted.Major Areas Inspected:Radiation Protection Program Including External Exposure Controls,Training Qualifications, Facilities & Equipment & Procedures & Documentation IR 05000382/19970281998-02-11011 February 1998 Insp Rept 50-382/97-28 on 971214-980131.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support Activities IR 05000382/19980011998-01-29029 January 1998 Insp Rept 50-382/98-01 on 980112-15.No Violations Noted. Major Areas Inspected:Implementation of Solid Radwaste Mgt & Radwaste/Matls Transportation Program.Quality Assurance Oversight,Training & Procedural Guidance Were Also Reviewed ML20198M2801998-01-12012 January 1998 Insp Rept 50-382/97-24 on 971102-1213.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20198C8871998-01-0505 January 1998 Insp Rept 50-382/97-26 on 971117-1205.No Violations Noted. Major Areas Inspected:Operator Activities Re Failure to Return Valve ACC-126A,auxiliary Component CWS Flow Control Valve,To Automatic Operation When Restoring CWS ML20198C4561998-01-0202 January 1998 Insp Rept 50-382/97-27 on 971117-1205.Violations Noted. Major Areas Inspected:Review of Licensee Identification That Plant Ventilation Sys Could Adversely Affect Level Indication for Refueling Water Storage Pool IR 05000382/19970181997-12-0505 December 1997 Insp Rept 50-382/97-18 on 971104-07.Violations Noted.Major Areas Inspected:Licensee Performance & Capabilities During full-scale,biennial Exercise of Emergency Plan & Implementing Procedures Performed IR 05000382/19970211997-12-0202 December 1997 Insp Rept 50-382/97-21 on 970922-26 & 1006-10.Violation Noted.Major Areas Inspected:Engineering,Maintenance & Mgt Meetings IR 05000382/19970221997-11-19019 November 1997 Insp Rept 50-382/97-22 on 970921-0001.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19970231997-11-0404 November 1997 Insp Rept 50-382/97-23 on 971006-10.No Violations Noted. Major Areas Inspected:Liquid & Gaseous Radioactive Effluent Waste Mgt Program Including Organization & Mgt Controls & Radioactive Effluent Monitoring IR 05000382/19970191997-10-24024 October 1997 Partially Withheld Insp Rept 50-382/97-19 on 970922-26 (Ref 10CFR73.21).No Violations Identified.Major Areas Inspected: Plant Support Re Land Vehicle Control Measures & Security Program IR 05000382/19970171997-10-23023 October 1997 Insp Rept 50-382/97-17 on 970929-1003.Violations Noted. Major Areas Inspected:Licensed Operator Requalification Program Following Guidelines in Insp Procedure 71001, Licensed Operator Requalification Program Evaluation IR 05000382/19970161997-10-17017 October 1997 Insp Rept 50-382/97-16 on 970810-0920.Violations Noted: Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19970201997-10-0909 October 1997 Insp Rept 50-382/97-20 on 970922-26.Violations Noted.Major Areas Inspected:External & Internal Exposure Control Programs,Surveys,Monitoring & Control of Radioactive Matl & Quality Assurance 1999-09-08
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000382/19990201999-10-21021 October 1999 Insp Rept 50-382/99-20 on 990815-0925.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support Activities IR 05000382/19990141999-10-19019 October 1999 Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Major Areas Inspected:Operator Requalification Training Program IR 05000382/19990181999-09-29029 September 1999 Insp Rept 50-382/99-18 on 990830-0902.Violations Noted.Major Areas Inspected:Implementation of NRC-approved Fire Protection Program IR 05000382/19990191999-09-27027 September 1999 Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted. Major Areas Inspected:Plant Support IR 05000382/19990151999-09-14014 September 1999 Insp Rept 50-382/99-15 on 990719-23 with in Ofc Insp Until 0819.No Violations Noted.Major Areas Inspected:Assessment of 10CFR50.59 Safety Evaluation Program & Review of Previous Insp Findings Involving Tornado Missile Protection IR 05000382/19990071999-09-0808 September 1999 Insp Rept 50-382/99-07 on 990601-11.Noncited Violations Identified.Major Areas Inspected:Operations IR 05000382/19990161999-09-0101 September 1999 Insp Rept 50-382/99-16 on 990704-0814.Noncited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support IR 05000382/19990101999-08-11011 August 1999 Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Major Areas Inspected:Solid Radioactive Waste Mgt & Radioactive Matl Transportation Programs IR 05000382/19990131999-07-15015 July 1999 Insp Rept 50-382/99-13 on 990523-0703.Noncited Violations Noted.Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities IR 05000382/19990121999-06-21021 June 1999 Insp Rept 50-382/99-12 on 990524-27.No Violations Noted. Major Areas Inspected:Operational Status of Licensee Emergency Preparedness Program IR 05000382/19990111999-06-18018 June 1999 Insp Rept 50-382/99-11 on 990524-28.No Violations Noted. Major Areas Inspected:Implementation of Liquid & Gaseous Radwaste Effluent Mgt Program,Status of Effluent Radiation Monitors & Counting Room Instruments IR 05000382/19990091999-06-0303 June 1999 Insp Rept 50-382/99-09 on 990411-0522.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19990061999-05-18018 May 1999 Insp Rept 50-382/99-06 on 990405-09.Non-cited Violations Identified.Major Areas Inspected:Issue Previously Identified During Architect Engineering Insp Which Documented NRC Insp Rept 50-382/98-201 IR 05000382/19990051999-05-10010 May 1999 Insp Rept 50-382/99-05 on 990228-0410.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support ML20206F4801999-05-0303 May 1999 Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Noted & Being Considered for Escalated Eas.Major Areas Inspected:Plant Support Including Licensee Access Authorization Program IR 05000382/19990041999-04-0909 April 1999 Insp Rept 50-382/99-04 on 990301-19.One Violation Occurred & Being Treated as Noncited Violation.Major Areas Inspected: Review of Licensee Implementation of Facility ISI Program & Followup Review of Reactor Trip Breaker Performance IR 05000382/19990021999-04-0505 April 1999 Insp Rept 50-382/99-02 on 990117-0227.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support Activities IR 05000382/19990031999-03-26026 March 1999 Insp Rept 50-382/99-03 on 990308-12.Violations Noted.Major Areas Inspected:Radiation Protection Program Focusing on RF09 Refueling Outage Activities IR 05000382/19990011999-03-0303 March 1999 Partially Deleted Insp Rept 50-382/99-01 on 990125-29 & 0208-12 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Plant Support IR 05000382/19980181998-12-21021 December 1998 Insp Rept 50-382/98-18 on 981018-1128.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19980151998-11-24024 November 1998 Insp Rept 50-382/98-15 on 980906-1017.No Violations Noted. Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities IR 05000382/19980131998-11-17017 November 1998 Insp Rept 50-382/98-13 on 980831-0901 & 981005-08.No Violations Noted.Major Areas Inspected:Maint Using Guidance of Temp Instruction 2515/137, Insp of Medium-Voltage & Low-Voltage Power Circuit Breakers ML20155D0561998-10-29029 October 1998 Insp Rept 50-382/98-17 on 981005-08.Violations Noted. Major Areas Inspected:Routine Review of Radiation Protection Program Activities ML20155D5111998-10-27027 October 1998 Partially Withheld Insp Rept 50-382/98-16 on 980914-18. Violations Noted.Major Areas Inspected:Licensee Physical Security Program.Portions Withheld (Ref 10CFR2.790) ML20154L1281998-10-0909 October 1998 Insp Rept 50-382/98-14 on 980726-0905.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19980121998-08-21021 August 1998 Insp Rept 50-382/98-12 on 980614-0725.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19992011998-07-27027 July 1998 Insp Rept 50-382/99-201 on 990511-0619.No Violations Noted Major Areas Inspected:Engineering IR 05000382/19980101998-07-20020 July 1998 Insp Rept 50-382/98-10 on 980622-26.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program Including Access Authorization,Alarm Stations,Protected Area Access Control of Personnel & Packages & Vehicles IR 05000382/19980091998-07-10010 July 1998 Insp Rept 50-382/98-09 on 980503-0613.Violations Noted.Major Areas Inspected:Aspects of Operations,Maint,Engineering & Plant Support Activities.Fire Door in Reactor Auxiliary Bldg Was Observed to Be Open W/No Controls in Place IR 05000382/19980081998-05-29029 May 1998 Insp Rept 50-382/98-08 on 980322-0502.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20217B6981998-04-21021 April 1998 Insp Rept 50-382/98-06 on 980201-0321.Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000382/19980021998-03-20020 March 1998 Insp Rept 50-382/98-02 on 980202-20.No Violations Noted. Major Areas Inspected:Current Performance & Effectiveness of Corrective Action Program Including Audits & Assessments, Operations & Engineering ML20216E1461998-03-12012 March 1998 Insp Rept 50-382/98-07 on 980302-06.Violations Noted.Major Areas Inspected:Plant Support ML20216E5991998-03-12012 March 1998 Insp Rept 50-382/98-05 on 980202-12.Violations Noted.Major Areas Inspected:Licensee Physical Security Program ML20216E7621998-03-12012 March 1998 Insp Rept 50-382/97-25 on 971201-980205.Violations Noted. Major Areas Inspected:Maint & Engineering IR 05000382/19980031998-03-10010 March 1998 Insp Rept 50-382/98-03 on 980216-20.No Violations Noted. Major Areas Inspected:Operational Status of Emergency Preparedness Program ML20203L2171998-03-0303 March 1998 Insp Rept 50-382/98-04 on 980202-06.Violations Noted.Major Areas Inspected:Radiation Protection Program Including External Exposure Controls,Training Qualifications, Facilities & Equipment & Procedures & Documentation IR 05000382/19970281998-02-11011 February 1998 Insp Rept 50-382/97-28 on 971214-980131.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support Activities IR 05000382/19980011998-01-29029 January 1998 Insp Rept 50-382/98-01 on 980112-15.No Violations Noted. Major Areas Inspected:Implementation of Solid Radwaste Mgt & Radwaste/Matls Transportation Program.Quality Assurance Oversight,Training & Procedural Guidance Were Also Reviewed ML20198M2801998-01-12012 January 1998 Insp Rept 50-382/97-24 on 971102-1213.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20198C8871998-01-0505 January 1998 Insp Rept 50-382/97-26 on 971117-1205.No Violations Noted. Major Areas Inspected:Operator Activities Re Failure to Return Valve ACC-126A,auxiliary Component CWS Flow Control Valve,To Automatic Operation When Restoring CWS ML20198C4561998-01-0202 January 1998 Insp Rept 50-382/97-27 on 971117-1205.Violations Noted. Major Areas Inspected:Review of Licensee Identification That Plant Ventilation Sys Could Adversely Affect Level Indication for Refueling Water Storage Pool IR 05000382/19970181997-12-0505 December 1997 Insp Rept 50-382/97-18 on 971104-07.Violations Noted.Major Areas Inspected:Licensee Performance & Capabilities During full-scale,biennial Exercise of Emergency Plan & Implementing Procedures Performed IR 05000382/19970211997-12-0202 December 1997 Insp Rept 50-382/97-21 on 970922-26 & 1006-10.Violation Noted.Major Areas Inspected:Engineering,Maintenance & Mgt Meetings IR 05000382/19970221997-11-19019 November 1997 Insp Rept 50-382/97-22 on 970921-0001.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19970231997-11-0404 November 1997 Insp Rept 50-382/97-23 on 971006-10.No Violations Noted. Major Areas Inspected:Liquid & Gaseous Radioactive Effluent Waste Mgt Program Including Organization & Mgt Controls & Radioactive Effluent Monitoring IR 05000382/19970191997-10-24024 October 1997 Partially Withheld Insp Rept 50-382/97-19 on 970922-26 (Ref 10CFR73.21).No Violations Identified.Major Areas Inspected: Plant Support Re Land Vehicle Control Measures & Security Program IR 05000382/19970171997-10-23023 October 1997 Insp Rept 50-382/97-17 on 970929-1003.Violations Noted. Major Areas Inspected:Licensed Operator Requalification Program Following Guidelines in Insp Procedure 71001, Licensed Operator Requalification Program Evaluation IR 05000382/19970161997-10-17017 October 1997 Insp Rept 50-382/97-16 on 970810-0920.Violations Noted: Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19970201997-10-0909 October 1997 Insp Rept 50-382/97-20 on 970922-26.Violations Noted.Major Areas Inspected:External & Internal Exposure Control Programs,Surveys,Monitoring & Control of Radioactive Matl & Quality Assurance 1999-09-08
[Table view] Category:UTILITY
MONTHYEARIR 05000382/19900221990-10-23023 October 1990 Insp Rept 50-382/90-22 on 900905-1001.Violations Noted.Major Areas Inspected:Followup of Events,Monthly Maint & Surveillance Observation,Operational Safety Verification, Followup of Previously Identified Items & LER Followup IR 05000382/19900211990-10-12012 October 1990 Insp Rept 50-382/90-21 on 900910-14.No Violations Noted. Major Areas Inspected:Liquid & Gaseous Radwaste Mgt Program IR 05000382/19902001990-09-10010 September 1990 Interfacing Sys LOCA Insp Rept 50-382/90-200 on 900730-0810. Major Areas Inspected:Plant Design Features,Sys,Equipment, Procedures,Operations Activities & Human Actions That Could Affect Initiation or Progress of Interfacing Sys LOCA IR 05000382/19900171990-08-27027 August 1990 Insp Rept 50-382/90-17 on 900625-29.No Violations or Deviations Noted.Major Areas Inspected:Operational Status of Emergency Preparedness Program Including Changes to Emergency Plans & EPIPs & Changes to Emergency Facilities IR 05000382/19900111990-07-29029 July 1990 Insp Rept 50-382/90-11 on 900625-29.No Violations or Deviations Noted.Major Areas Inspected:Radioactive Matl Transportation Program.Licensee Implemented Effective Program & Personnel Highly Qualified & Motivated IR 05000382/19900141990-07-17017 July 1990 Insp Rept 50-382/90-14 on 900625-29.Violation Noted.Major Areas Inspected:Containment Local Leak Rate Testing Data, Surveillance Test & Calibr Program & Followup of Previous Insp Findings IR 05000382/19900101990-07-0505 July 1990 Cancelled Insp Rept 50-382/90-10 IR 05000382/19900091990-06-26026 June 1990 Errata to Insp Rept 50-382/90-09,inserting Page 6a.No Violations or Deviations Noted ML20055C7821990-06-14014 June 1990 Insp Rept 50-382/90-09 on 900501-31.No Violations or Deviations Noted.One Unresolved Item Noted.Major Areas Inspected:Plant Status,Onsite Followup of Events,Monthly Surveillance Observation & Operational Safety Verification IR 05000382/19890231989-09-26026 September 1989 Insp Rept 50-382/89-23 on 890801-31.No Violations Noted. Major Areas Inspected:Plant Status,Onsite Followup of Events,Monthly Maint Observation,Monthly Surveillance Observation,Operational Safety Verification IR 05000382/19890251989-09-21021 September 1989 Insp Rept 50-382/89-25 on 890828-0901.No Violations or Deviations Noted.Major Areas Inspected:Radiological Environ Monitoring Program,Including Organization & Mgt Controls, Qualification & Training & Licensee QA & Contractor Audits IR 05000382/19890161989-09-15015 September 1989 Insp Rept 50-382/89-16 on 890717-21.Violation Noted.Major Areas Inspected:Operations Procedures IR 05000382/19890221989-08-0909 August 1989 Insp Rept 50-382/89-22 on 890701-31.Violation Noted.Major Areas Inspected:Onsite Followup of Events,Monthly Maint Observation,Monthly Surveillance Observation,Operational Safety Verification & LER Followup IR 05000382/19890201989-07-25025 July 1989 Insp Rept 50-382/89-20 on 890705.No Violations or Deviations Noted.Major Areas Inspected:Svc Failure of Shaft in Chilled Water Pump B IR 05000382/19890171989-07-14014 July 1989 Insp Rept 50-382/89-17 on 890601-30.Violations Noted.Major Areas Inspected:Onsite Followup of Events,Monthly Maint Observation,Monthly Surveillance Observation & Operational Safety Verification IR 05000382/19890181989-07-13013 July 1989 Insp Rept 50-382/89-18 on 890626-30.Noncited Violation Noted.Major Areas Inspected:Corrective Action Program & Licensee Actions on Previously Identified Findings IR 05000382/19890151989-07-0606 July 1989 Insp Rept 50-382/89-15 on 890605-09 & 20-21.No Violations or Deviations Noted.Major Areas Inspected:Storage of Emergency Diesel Generator Fuel Oil,Containment Bldg Temp Profiles & Action on Previously Identified Insp Findings IR 05000382/19890141989-07-0303 July 1989 Insp Rept 50-382/89-14 on 890522-26.No Violations or Deviations Noted.Major Areas Inspected:Radwaste Mgt & Effluent Control Programs & Review of Special & Semiannual Effluents Repts IR 05000382/19890131989-06-14014 June 1989 Insp Rept 50-382/89-13 on 890522-26.No Violations or Deviations Noted.Major Areas Inspected:Followup to Previous Insp Findings & Licensee Expeditious Actions Re Generic Ltr 88-17, Loss of Dhr ML20244C6951989-06-0808 June 1989 Insp Rept 50-382/89-12 on 890416-0531.Violations Noted. Major Areas Inspected:Monthly Maint Observation,Monthly Surveillance Observation,Onsite Followup of Events & Evaluation of Licensee QA Program Implementation IR 05000382/19890081989-05-16016 May 1989 Insp Rept 50-382/89-08 on 890301-0415.Violations Noted. Major Areas Inspected:Status,Monthly Maint Observation,Event Followup,Esf Walkdown & LER Followup IR 05000382/19890111989-05-0808 May 1989 Insp Rept 50-382/89-11 on 890327-31.Violations Noted.Major Areas Inspected:Engineering & Technical Support Activities & QA Audits of Activities IR 05000382/19890041989-04-18018 April 1989 Insp Rept 50-382/89-04 Cancelled ML20245C7281989-04-12012 April 1989 Insp Rept 50-382/89-07 on 890227-0303 & 890313-17.Violation Noted.Major Areas Inspected:Previously Identified Findings, Licensee self-assessment Capabilities & Procurement Activities ML20244A7551989-04-0303 April 1989 Insp Rept 50-382/89-09 on 890308-09.Violations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings Associated W/Testing,Low Recirculation Flow Condition & Corrective Maint of HPSI Pump B ML20247K3951989-03-25025 March 1989 Insp Rept 50-382/89-06 on 890201-28.Violations Noted.Major Areas Inspected:Plant Status,Monthly Maint Observation, Operational Safety Verification,Onsite Followup of Events, ESF Walkdown & Followup of Previously Identified Items IR 05000382/19890101989-03-15015 March 1989 Cancels Insp Rept 50-382/89-10.No Insp Rept Will Be Issued for Rept Number IR 05000382/19890011989-03-14014 March 1989 Insp Rept 50-382/89-01 on 890117-0210.Violations Noted.Major Areas Inspected:Maint Performance,Overall Plant Performance Re Maint,Mgt Support of Maint & Maint Implementation ML20247A5101989-03-14014 March 1989 Insp Rept 50-382/89-05 on 890213-17.Violation Noted.Major Areas Inspected:Licensee Action on Previously Identified Violations & Unresolved Items Re Equipment Qualification of Electric Equipment ML20235Z7771989-03-0303 March 1989 Insp Rept 50-382/89-02 on 890109-13.Violations Noted.Major Areas Inspected:Followup of Previous Insp Items,Followup of NRC Info Notices & Bulletins Applicable to Procurement & Insp of 10CFR21 Activities ML20235M7561989-02-16016 February 1989 Insp Rept 50-382/89-03 on 890101-31.Violations Noted.Major Areas Inspected:Plant Status,Monthly Surveillance Operation, Onsite Followup of Events,Diesel Generator Fuel Oil QA & NRC Bulletin 87-002 & LER Followup IR 05000382/19880271988-11-22022 November 1988 Insp Rept 50-382/88-27 on 881017-27 & 881101-07.Violations Noted.Major Areas Inspected:Licensee Actions on Previously Identified Items Re Equipment Documented in NRC Insp Rept 50-382/86-32 on 870416 ML20195J6561988-11-17017 November 1988 Insp Rept 50-382/88-25 on 880917-1031.Violations Noted. Major Areas Inspected:Plant Status,Onsite Followup of Events,Operational Safety Verification,Monthly Maint Observation & Monthly Surveillance Observation IR 05000382/19880261988-11-16016 November 1988 Insp Rept 50-382/88-26 on 881024-26.No Violations or Deviations Noted.Major Areas Inspected:Followup to Previous Insp Findings,Lers,Steam Generator Noise,& Replacement of Valve in Letdown Flow Sys IR 05000382/19880241988-11-0909 November 1988 Insp Rept 50-382/88-24 on 881011-13.No Violations or Deviations Noted.Eight Deficiencies Identified.Major Areas Inspected:Licensee Performance & Capabilities During Annual Exercise of Emergency Plan & Procedures IR 05000382/19880211988-10-12012 October 1988 Insp Rept 50-382/88-21 on 880801-0916.Violation & Deviation Noted.Major Areas Inspected:Plant Status,Onsite Followup of Events,Followup of Previously Identified Items,Operational Safety Verification & Monthly Maint Observation IR 05000382/19880231988-09-27027 September 1988 Insp Rept 50-382/88-23 on 880822-26 & 0919-23.Violations Noted.Major Areas Inspected:Potential Enforcement Findings Identified by Vendor Insp Branch in Insp Rept 50-382/87-19 ML20153D4311988-08-19019 August 1988 Insp Rept 50-382/88-19 on 880618-0731.Violations Noted. Major Areas Inspected:Enforcement Followup on Quality Verification Function Insp,Monthly Maint Observation, Allegation Followup & Operational Safety Verification ML20153C2521988-08-17017 August 1988 Insp Rept 50-382/88-20 on 880710-15.No Violations or Deviations Noted.Major Areas Inspected:Transportation of Radioactive Matls & Low Level Radwaste Mgt IR 05000382/19880181988-08-0909 August 1988 Insp Rept 50-382/88-18 on 880706-14.No Violations or Deviations Noted.Major Areas Inspected:Facility Emergency Operating Procedures,Including Control Room & Plant Walkdown,Simulator & Human factors-related Guidance ML20151E2391988-07-14014 July 1988 Insp Rept 50-382/88-13 on 880501-0617.Violations Noted.Major Areas Inspected:Monthly Maint Observation,Ler Followup, Containment Integrated Leak Rate Test,Plant Status & Followup of Previously Identified Items IR 05000382/19880171988-06-14014 June 1988 Insp Rept 50-382/88-17 on 880531-0603.One Violation & No Deviations Noted.Major Areas Inspected:Startup Testing IR 05000382/19880141988-06-13013 June 1988 Partially Withheld Insp Rept 50-382/88-14 on 880523-27 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Testing & Maint Program,Facility Lighting,Security Training & Qualification Plan & Safeguards Info Program IR 05000382/19880081988-06-0202 June 1988 Insp Rept 50-382/88-08 on 880316-0430.Violations Noted.Major Areas Inspected:Onsite Followup of Events,Monthly Maint Observation,Monthly Surveillance Observation,Refueling Activity Observation,Esf,Sys Walkdown & Plant Status IR 05000382/19880101988-06-0101 June 1988 Insp Rept 50-382/88-10 on 880418-22.Violations Noted.Major Areas Inspected:Licensee Corrective Action Program Effectiveness IR 05000382/19880121988-05-27027 May 1988 Insp Rept 50-382/88-12 on 880501-06.No Violations Noted. Major Areas Inspected:Radiation Protection Activities During Cycle 2 Refueling Outage ML20154S2301988-05-27027 May 1988 Insp Rept 50-382/88-16 on 880512-20.Potential Violation & Deviation Noted.Major Areas Inspected:Events Which Occurred & Actions Taken by Util Prior To,During & Subsequent to 880512 Incident Re Possible Loss of Shutdown Cooling IR 05000382/19882001988-05-16016 May 1988 Insp Rept 50-382/88-200 on 880201-12.Weaknesses Noted.Major Areas Inspected:Quality Verification Organization Ability to Identify,Resolve & Prevent Recurrence of safety-significant Deficiencies in Functional Areas of Plant Operations IR 05000382/19880111988-05-16016 May 1988 Insp Rept 50-382/88-11 on 880418-22.Violations Noted.Major Areas Inspected:Licensee Action on Previously Identified Insp Findings,Inservice Insp & 10CFR21 ML20153E3091988-04-26026 April 1988 Insp Rept 50-382/88-09 on 880404-08.No Violations or Deviations Noted.Major Areas Inspected:Licensee Surveillance Procedures & Records & Verification of RCS Leak Rates 1990-09-10
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000382/19990201999-10-21021 October 1999 Insp Rept 50-382/99-20 on 990815-0925.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support Activities IR 05000382/19990141999-10-19019 October 1999 Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Major Areas Inspected:Operator Requalification Training Program PNO-IV-99-038A, on 990929,restart of Waterford 3 Occurred. Cause Identified as Failed Seal Water Heat Exchanger Baffle. New Battle & Seal Assembled Were Installed & Reactor Coolant Pump 2B Was Returned to Svc Satisfactorily1999-10-0101 October 1999 PNO-IV-99-038A:on 990929,restart of Waterford 3 Occurred. Cause Identified as Failed Seal Water Heat Exchanger Baffle. New Battle & Seal Assembled Were Installed & Reactor Coolant Pump 2B Was Returned to Svc Satisfactorily IR 05000382/19990181999-09-29029 September 1999 Insp Rept 50-382/99-18 on 990830-0902.Violations Noted.Major Areas Inspected:Implementation of NRC-approved Fire Protection Program IR 05000382/19990191999-09-27027 September 1999 Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted. Major Areas Inspected:Plant Support PNO-IV-99-038, on 990910,operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.New Baffle & Seal Assembly Were Installed & Plant Was Returned to Power Operations on 9908101999-09-15015 September 1999 PNO-IV-99-038:on 990910,operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.New Baffle & Seal Assembly Were Installed & Plant Was Returned to Power Operations on 990810 IR 05000382/19990151999-09-14014 September 1999 Insp Rept 50-382/99-15 on 990719-23 with in Ofc Insp Until 0819.No Violations Noted.Major Areas Inspected:Assessment of 10CFR50.59 Safety Evaluation Program & Review of Previous Insp Findings Involving Tornado Missile Protection IR 05000382/19990071999-09-0808 September 1999 Insp Rept 50-382/99-07 on 990601-11.Noncited Violations Identified.Major Areas Inspected:Operations IR 05000382/19990161999-09-0101 September 1999 Insp Rept 50-382/99-16 on 990704-0814.Noncited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support PNO-IV-99-032A, on 990801,Waterford 3 Operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.Pump Was Secured Immediately Following Plant Sd.New Baffle & Seal Assembly Was Installed1999-08-12012 August 1999 PNO-IV-99-032A:on 990801,Waterford 3 Operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.Pump Was Secured Immediately Following Plant Sd.New Baffle & Seal Assembly Was Installed IR 05000382/19990101999-08-11011 August 1999 Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Major Areas Inspected:Solid Radioactive Waste Mgt & Radioactive Matl Transportation Programs PNO-IV-99-032, on 990801,Waterford 3 Operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.Pump Was Secured Immediately Following Plan Shutdown.Resident Inspectors Will Monitor1999-08-0303 August 1999 PNO-IV-99-032:on 990801,Waterford 3 Operators Manually Tripped Reactor from 100% Power in Response to Indications of Failure of RCP 2B Seal.Pump Was Secured Immediately Following Plan Shutdown.Resident Inspectors Will Monitor IR 05000382/19990131999-07-15015 July 1999 Insp Rept 50-382/99-13 on 990523-0703.Noncited Violations Noted.Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities IR 05000382/19990121999-06-21021 June 1999 Insp Rept 50-382/99-12 on 990524-27.No Violations Noted. Major Areas Inspected:Operational Status of Licensee Emergency Preparedness Program IR 05000382/19990111999-06-18018 June 1999 Insp Rept 50-382/99-11 on 990524-28.No Violations Noted. Major Areas Inspected:Implementation of Liquid & Gaseous Radwaste Effluent Mgt Program,Status of Effluent Radiation Monitors & Counting Room Instruments ML20196C9461999-06-15015 June 1999 Notice of Violation from Insp Completed on 990422.Violation Noted:Licensee Failed to Consider Info Contained During Background Investigation Before Granting Temporary Unescorted Access to Contractor Employee IR 05000382/19990091999-06-0303 June 1999 Insp Rept 50-382/99-09 on 990411-0522.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20209B8581999-05-25025 May 1999 EN-98-046A:on 990524,staff Withdrew Proposed Civil Penalty in Amount of $110,000 Issued to Licensee.Action Based on Severity Level III Problems Associated with ECCS & Afws IR 05000382/19990061999-05-18018 May 1999 Insp Rept 50-382/99-06 on 990405-09.Non-cited Violations Identified.Major Areas Inspected:Issue Previously Identified During Architect Engineering Insp Which Documented NRC Insp Rept 50-382/98-201 IR 05000382/19990051999-05-10010 May 1999 Insp Rept 50-382/99-05 on 990228-0410.Non-cited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support ML20206F4801999-05-0303 May 1999 Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Noted & Being Considered for Escalated Eas.Major Areas Inspected:Plant Support Including Licensee Access Authorization Program IR 05000382/19990041999-04-0909 April 1999 Insp Rept 50-382/99-04 on 990301-19.One Violation Occurred & Being Treated as Noncited Violation.Major Areas Inspected: Review of Licensee Implementation of Facility ISI Program & Followup Review of Reactor Trip Breaker Performance IR 05000382/19990021999-04-0505 April 1999 Insp Rept 50-382/99-02 on 990117-0227.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support Activities IR 05000382/19990031999-03-26026 March 1999 Insp Rept 50-382/99-03 on 990308-12.Violations Noted.Major Areas Inspected:Radiation Protection Program Focusing on RF09 Refueling Outage Activities IR 05000382/19990011999-03-0303 March 1999 Partially Deleted Insp Rept 50-382/99-01 on 990125-29 & 0208-12 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected:Plant Support ML20207F1581999-03-0303 March 1999 Notice of Violation from Insp on 990125-29 & 0208-12. Violation Noted:Inspector Determined That Waterford Audits SA-98-025.1 & SA-98-036.1,dtd 980916,were Conducted by Individuals Not Independent of Program Mgt Being Audited IR 05000382/19980181998-12-21021 December 1998 Insp Rept 50-382/98-18 on 981018-1128.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19980151998-11-24024 November 1998 Insp Rept 50-382/98-15 on 980906-1017.No Violations Noted. Major Areas Inspected:Aspects of Operations,Maint, Engineering & Plant Support Activities PNO-IV-98-054, on 981117,plant Shutdown Greater than 72 H Due to Unidentified Leak.Investigations by Licensee Verified That Leakage Occurred from RCP 2b Seal Area1998-11-19019 November 1998 PNO-IV-98-054:on 981117,plant Shutdown Greater than 72 H Due to Unidentified Leak.Investigations by Licensee Verified That Leakage Occurred from RCP 2b Seal Area IR 05000382/19980131998-11-17017 November 1998 Insp Rept 50-382/98-13 on 980831-0901 & 981005-08.No Violations Noted.Major Areas Inspected:Maint Using Guidance of Temp Instruction 2515/137, Insp of Medium-Voltage & Low-Voltage Power Circuit Breakers ML20155D0561998-10-29029 October 1998 Insp Rept 50-382/98-17 on 981005-08.Violations Noted. Major Areas Inspected:Routine Review of Radiation Protection Program Activities ML20155D0411998-10-29029 October 1998 Notice of Violation from Insp on 981005-08.Violation Noted: Inspectors Identified That Radiation Surveys to Evaluate Extent of Radiation Levels Had Not Been Performed Prior to Operations Personnel Entering Area ML20155D5111998-10-27027 October 1998 Partially Withheld Insp Rept 50-382/98-16 on 980914-18. Violations Noted.Major Areas Inspected:Licensee Physical Security Program.Portions Withheld (Ref 10CFR2.790) ML20155D5021998-10-27027 October 1998 Notice of Violation from Insp on 980914-18.Violation Noted: Performance Tests of Protected Area Detection Sys Identified That Two Detection Zones Did Not Meet Design Criteria to Detect Test Individuals ML20154L0831998-10-0909 October 1998 Notice of Violation from Insp on 980726-0905.Violation Noted:On 980721,NRC Inspectors Found Door 206,vital Area Portal,Unlocked & Not in Alarm at Central Alarm Station ML20154L1281998-10-0909 October 1998 Insp Rept 50-382/98-14 on 980726-0905.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-IV-98-045, on 980926,Unit 3 Declared Unusual Event of Hurricane Warning in St Charles Parish.River Bend Station Continued to Operate at Full Power Since Hurricane Force Winds Were Not Predicted in Vicinity of Site1998-09-28028 September 1998 PNO-IV-98-045:on 980926,Unit 3 Declared Unusual Event of Hurricane Warning in St Charles Parish.River Bend Station Continued to Operate at Full Power Since Hurricane Force Winds Were Not Predicted in Vicinity of Site PNO-IV-98-040, on 980917,licensee Commenced Shutdown of Reactor in Order to Replace Pressurizer Code Safety Valve That Had Been Experiencing Increased Leakage.Licensee Plans to Restart Facility on 9809231998-09-18018 September 1998 PNO-IV-98-040:on 980917,licensee Commenced Shutdown of Reactor in Order to Replace Pressurizer Code Safety Valve That Had Been Experiencing Increased Leakage.Licensee Plans to Restart Facility on 980923 IR 05000382/19980121998-08-21021 August 1998 Insp Rept 50-382/98-12 on 980614-0725.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000382/19992011998-07-27027 July 1998 Insp Rept 50-382/99-201 on 990511-0619.No Violations Noted Major Areas Inspected:Engineering IR 05000382/19980101998-07-20020 July 1998 Insp Rept 50-382/98-10 on 980622-26.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program Including Access Authorization,Alarm Stations,Protected Area Access Control of Personnel & Packages & Vehicles ML20236P2431998-07-10010 July 1998 Notice of Violation from Insp on 980503-0613.Violation Noted:On 980521,AP UNT-005-013 Was Not Implemented in That Impairment to Fire Door D150 Was Not Controlled IR 05000382/19980091998-07-10010 July 1998 Insp Rept 50-382/98-09 on 980503-0613.Violations Noted.Major Areas Inspected:Aspects of Operations,Maint,Engineering & Plant Support Activities.Fire Door in Reactor Auxiliary Bldg Was Observed to Be Open W/No Controls in Place ML20249A9611998-06-16016 June 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.Violation Noted:Licensee Identified That Calculated Peak Fuel Cladding Temp Would Have Exceeded 2200 F Using Licensing Basis Analysis & HPSI Flow ML20151R9131998-06-0909 June 1998 EN-98-046:on 980616,notice of Proposed Imposition of Civil Penalty in Amount of $110,000 Issued to Licensee.Action Based on Level III Problem Involving HPSI Flow Issues at Waterford-3 Facility IR 05000382/19980081998-05-29029 May 1998 Insp Rept 50-382/98-08 on 980322-0502.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20248F6801998-05-29029 May 1998 Notice of Violation from Insp on 980322-0502.Violation Noted:Licensee Failed to Establish Adequate Procedures for Operation of EDG When in No or Low Electrical Loading Condition in That No Specific Guidance Provided IR 05000382/19980991998-04-24024 April 1998 SALP Rept 50-382/98-99 for 961201-980321 ML20217B6731998-04-21021 April 1998 Notice of Violation from Insp on 980201-0321.Violation Noted:On Past Occasions,Engineer Operated Governor Valve on Emergency Feedwater Turbine W/O Direction or Concurrence of Shift Superintendent or Control Room Supervisor ML20217B6981998-04-21021 April 1998 Insp Rept 50-382/98-06 on 980201-0321.Violations Noted.Major Areas Inspected:Operations,Maint & Engineering 1999-09-08
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-382/86-28 License: NPF-38 Docket: 50-382 Licensee: Louisiana Power & Light Company (LP&L)
N-80 317 Baronne Street New Orleans, Louisiana 70160 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection Conducted: November 17-21, 1986 Inspector: kN 3//3/F7
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John Boardman, Reactor Inspector Operations Da'te Section, Reactor Safety Branch Accompanied by: Howard Stromberg, EG&G ,
Clarke Kido, EG&G Approved By: h/
D. M. Hunnicutt, Chief, Operations Section 3//3/F7 Date '
Reactor Safety Branch Inspection Summary:
Inspection Conducted November 17-21, 1986 (Report 50-382/86-28)
Areas Inspected: A Region IV team inspection of licensee maintenance activities was performed. The inspection covered maintenance program implementation, maintenance program, instrument and control maintenance, and electrical maintenanc Results: Of the four areas inspected, one violation was identified (failure to comply with procedures for control of temporary alterations).
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DETAILS Persons Contacted
- J. Dewease, Senior Vice President, Nuclear Operations
- R. P. Barkhurst, Vice President, Nuclear Operations
- K. L. Brewster, Lic. Eng., Operational Licensing
- N. S. Carns, Plant Manager
- K. W. Cook, Nuclear Safety & Regulatory Affairs Manager
- C R. Gains, Operations Interface
- T. F. Gerrets, Nuclear QA Manager
- J. R. McGaha, 0&M Assistant Plant Manager
- F. J. Engle Bracht, Nuclear Administrative Services Manager
- S. A. Alleman, Assistant Plant Manager, Technical Services
- T. H. Smith, Maintenance Superintendent
- A. S. Lockhart, Nuclear Operational Safety Analysis Manager
- K. L. Brewster, Licensing Engineer - Operational Licensing T. Moore, Electrical Supervisor T. Smith, Maintenance Superintendent B. Thigpen, Mechanical Maintenance Assistant Superintendent J. Begnaud, Mechanical Supervisor, Nuclear L. Lehmann, Mechanical Supervisor, Nuclear The NRC inspector also interviewed additional licensee and contractor personnel during the inspectio * Denotes those attending the exit interview on November 21, 198 The senior resident inspector attended the exit intervie . Actions on Previous Findings (Closed) Unresolved Item (50-382/8504-02) Closure of Ebasco purchase orders. For the orders included in the inspector's sample, licensee personnel provided documentation of closure satisfying the NRC inspector that no significant problem appears to exist in this are . Temporary Alteration Control During the inspection, the NRC inspector reviewed the following procedures provided by licensee personnel:
UNT-5-004, Revision 3, Administrative Procedure Temporary Alteration Control
ME-7-002, Revision 5. Maintenance Procedure Molded-Case Circuit Breakers and Thermal Overload Relays
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UNT-5-004, Revision 3. Section 3.1 defines a temporary alternation as any short tem addition to, removal from or change in the function of a system or any of its components which is not in accordance with approved-Waterford III desig Specific controls are required by UNT-5-004, Revision 3. for temporary alterations, unless prescribed controls are contained in procedures which perform temporary alteration ME-7-002, Revision 5. specifies and defines performance testing of molded-case circuit breakers. Certain tests, such as the instantaneous trip test, Section 8.5, specify removal of current-limiting fuses and their replacement with shorting devices for the performance of the tes No note, or procedure step, specifies or requires, the removal of the shorting devices, and replacement of the fuses required for breaker operability after completion of testin Procedure ME-7-002, Revision 5, does not reference procedure UNT-5-00 ' Licensee personnel indicated that temporary replacement of fuses with shorting bars, particularly for shop testing, had not been considered to be a temporary modificatio Failure to comply with UNT-5-004, Revision 3, Sections 4.0 and 5.0, and subsections thereto, in the removal and replacement of fuses for testing of circuit breakers is an apparent violation of 10 CFR Part 50, Appendix B, Criterion V, and ANSI N18.7-1976, Section 5. (382/8628-01) Maintenance Program The NRC inspector reviewed the licensee's maintenance progra Appropriate personnel in management, supervision, and crafts were interviewed concerning their areas of responsibility and their understanding of the applicable procedure The plant was preparing for its first refueling outage when the inspection was conducted. Certain corrective and many preventive maintenance actions had been rescheduled to be accomplished during the outage. Various training classes had been held to prepare personnel for work on components such as valves, pumps, snubbers, and energency diesel generator Personnel were temporarily reassigned to handle responsibilities in maintenance planning and scheduling, plant engineering, and maintenance trainin . .
Based on interviews with maintenance personnel and observation of Condition Identifications Work Authorization (CIWAs) 28583, 29923, and 23768 it appeared to the NRC inspector that the licensee relies heavily upon worker experience and verbal communication in the performance of maintenanc Maintenance procedures required careful interpretation and were usually augmented by the worker's personal experience or detailed instructions from the most cognizant supervisor. A concern of the NRC inspector was that some procedures as written may be too vague for a worker
- with limited experience to properly perform the task. It appeared that procedural corrections and clarifications considered necessary by maintenance personnel were not being routed to the planner so that the procedures could be amended, as appropriat This concern was discussed with the licensee, who indicated that a reorganization is scheduled shortly to more closely integrate personnel and responsibilities. In implementation of this concept, the snubber maintenance program is undergoing review by plant engineering, maintenance planning, and mechanical maintenanc The NRC inspector reviewed three maintenance activities (CIWAs 28583, 29923, and 23768). The CIWAs were reviewed to determine craft compliance with maintenance procedures, adequacy of maintenance procedures, and if required procedures and materials were present during work performanc Two completed corrective maintenance and three preventive maintenance CIWAs were reviewe In addition, the maintenance history files for the essential chillers were reviewed to determine if previous Freon leaks had occurred. No concerns were identified. The following mechanical maintenance tasks were reviewed
- CIWA 25630, boric acid makeup tank pump discharge drain valve seat leak repair, CIWA 27322, essential chiller B temperature controller Freon leak repai PM Task Carri MWORFRAB2, essential chiller WC1AB refrigerant filter changeou PM Task Card MWORFRAB2, essential chiller WCIAB compressor oil and filter changeou EQ Task Card MW0EFWP02, emergency feedwater pump AB (Terry Turbine)
oil system inspect, clean, and change filter Two additional concerns were identified during this review of the maintenance progra The first was that a plant wide trending analysis program did not appear to be implemented. The second concern was that there did not appear to be a procedure being used that ensured consistency in the documents transferred to storage. In a number of packages (see Sections 4 and 5 below) there were sections that did not appear to be completed as required, and at times it could not be verified if all
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applicable documents were in the stored document files. This will remain an open item (382/8628-02) pending further review during a subsequent inspectio . Maintenance Program Implementation The NRC inspector obtained a list of maintenance activities which were scheduled for the week of November 17-21, 1986. He selected three for inspection to determine compliance with the regulations and the Waterford 3 Administrative Procedure The three maintenance activities were detailed on Condition Identification and Work Authorization (CIWAs) for the following corrective maintenance:
troubleshoot Freon leak found at electrical box on the compressor to Essential Chiller AB, troubleshoot RCS leakage past seals on Charging Pump B, and preventive maintenance of type PSA-3 mechanical snubber The CIWAs were identified as CIWA 28583, 29923, and 23768, respectivel Each CIWA was reviewed for authorizing signatures, spare parts control, inspection adequacy, mechanical qualification, adequacy of maintenance performed and post-maintenance functional testing and restoration. The CIWA's were also reviewed to determine compliance with the requirements of the following procedures:
MM-1-002, Revision 2, " Mechanical Maintenance Practice," dated August 24, 198 MD-1-007, Revision 2, " Preventive Maintenance Task Identification,"
dated November 15, 198 "
MD-1-004, Revision 6, " Preventive Maintenance Scheduling," dated May 21, 198 *
UNT-5-002, Revision 5, " Administrative Procedure, Condition Identification and Work Authorization (CIWA)," dated January 13, 198 *
MD-1-011, Revision 3, Maintenance Procedure Development, Review, Approval, Change, Revision, Deletion MD-1-014, Revision 1, " Administrative Procedure, Conduct of Maintenance," dated November 21, 198 MM-6-023, Revision 1, " Mechanical Snubber (Shock Arresters)
Maintent.nce," dated October 21, 198 .
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MM-7-011, Revision 3, " Mechanical Snubber Test," dated November 14, 198 The troubleshooting of the Essential Chiller AB Freon leak was witnessed by the NRC inspector. The NRC inspector reviewed the job from receipt of the CIWA by the maintenance mechanic, through the mechanic's disassembly and inspection of the pump out compressor, his written work order instructing the planner to contact the vendor for detailed information and replacement parts, the planner's purchase order for the spare parts, and the maintenance supervisor's commitment to reassemble and test the chille Upon disassembly of the electrical box on the pump out compressor, the mechanics found that an unused electrical connection had been improperly sealed with a fibrous plug, and a cardboard and plastic spacer. A telephone call to the compressor manufacturer indicated that a double locking nut connection should have been made. The licensee amended the CIWA to plug the connection as specified by the manufacturer. The licensee intended to correct only Chiller AB, although there are two other identical chillers at the plant.
, The NRC inspector had two concerns relating to this maintenance work. The first concern was that the technical manual for the pump-out compressor lacked sufficient detail to describe the correct electrical connection When the licensee started work, he determined that the technical manual did not provide sufficient detail to allow repairs to be made. When disassembly was completed, the manufacturer was called ar.d his advice was followed to make repairs. These licensee actions adequately addressed this concer A second concern was that the licensee did not intend to inspect the other two essential chillers unless a similar Freon leak occurred, at which time the licensee would follow the same corrective action. The licensee was asked to confirm that the unused electrical connections for each essential chiller pump out compressor has been properly plugged and ensure that preventive measures are in place to prevent recurrence of the Freon leak problem. The licensee's actions had no significant effect on safety. The components were safety-related. The licensee was not correcting a known common mode failure mechanism that affected 2 of 3 safety system The troubleshooting of a charging pump seal leak was followed by the NRC inspector. The NRC inspector witnessed the job from receipt of the CIWA by the mechanic, through the obtaining of spare parts, verification of the status of equipment tagged out, and clearance for access to the vital are The NRC inspector discontinued observations during seal replacement and functional testing because of work area health physics requirement The licensee determined that the root cause of the seal failure was deficient packing. No concerns were identifie _ _ _ _ - _ _ _ . _ . _ _ _ _ _ . _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _
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The NRC inspector followed preventive maintenance of Type PSA-3 mechanical snubbers that was in progress. Licensee personnel used procedure MM-6-023, Revision 1. During work, the NRC inspector observed that several steps in MM-6-023 were not followed (for example, step:. 8.2.1.10, .11, and .12),
since they applied only to a major overhaul of the snubber. Prior approval to omit the steps had not been documented, or authorized by the maintenance supervisor. The mechanic's work was based on procedure MM-6-023, in general, plus " hands-on" experience gained from a snubber workshop held at the vendor's factory. Revision 1 of procedure MM-6-023 was verified to be the latest revision controlled by the document records departmen Discussions with the mechanic, supervisor, and planner indicated that the snubber procedure would be revised in the near futur The NRC inspector noted a weakness dealing with the administrative aspects of the above maintenance. As stated in the previous paragraphs, the mechanics did not perform several steps that the craftsmen knew or believed, were optional. This practice can result in an error and maintenance which is not approved. The NRC inspector's concern was that a junior mechanic was undergoing on-the-job training by a senior mechanic who did not follow the maintenance procedure as written. The licensee was asked to review procedures MM-6-023 and MM-7-11 and ensure that the appropriate steps are identified for performance of all levels of maintenance specified by these procedures. This review will ensure compliance with step 14 of Attachment 6.10 to Procedure MD-1-011, which indicates that an optional step in a maintenance procedure shall be clearly identified as suc . Licensee Instrumentation Maintenance Program The NRC inspector performed an inspection of the maintenance program in the instrument and control areas in accordance with Inspection and Enforcement Manual Section 62704 and the Waterford 3 Administrative Procedures. Maintenance history, calibration records, procedures, work item tracking forms, and maintenance work request forms were obtained and reviewed. Selected instrument and control supervisors and technicians of the I&C Maintenance Organization were interviewed to determine their areas of responsibilities, functions, and qualification Two work activities in progress were witnessed by the NRC inspector to determine if the technicians were following appropriate maintenance procedures. The two activities were: (1) MI-5-160, Revision 1, Calibration of Plant Protection System Test and Calibration Card and Digital Volt Meter (DVM), and (2) MI-3-350, Revision 5, Containment Purge Isolation Area Radiation Monitor Channel "A" or "B" Functional Test ARM-IR-5024S 50255, 5027 There were a number of discrepancies noted during the performance of these activitie The following are examples of procedures not being followed: Step 8.4 of MI-5-160 (Calibration of Plant Protection System Test and Calibration Card and DVM) indicated that the DVM should be turned on and set to Volt Direct Current (VDC) Auto with the "As Found" block to be filled in on Attachment 10.1. The technicians performing the
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calibration understood this step to mean the test instrument and not the DVM being calibrated. An entry was not made in Attachment 1 for the DVM. The actions were not consistent with the procedure. It should be noted that the instruction was misleadingly vague, since it appeared to be applicable to the test instrument instead of the DVM which is constantly energized and does not have an " Auto" positio Step 8.28 of MI-5-160 required that a calibration sticker be attached to the DV Instead it was attached to the panel above the DV Step 8.1.1 of MI-3-350 (Containment Purge Isolation Area Radiation Monitor Channel "A" or "B" Functional Test (ARM-IR-5027S)) required a jumper to be used when the Containment Purge Isolation Valves are shut. Discussions with the technicians indicated that the jumper installation was not always performed. Operations personnel dictated jumper installation and decided whether or not a potential existed for the valves to be operated before testing was completed. The procedure does not allow this choice.
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The second item found during work observations was that the procedures were in error in a number of step The following are examples where errors were noted: Step 8.19 of MI-5-160 indicated that both " Bistable Select" switches should be verified in the "Of f" position. Only one has an off position; the other has a line indicating of Step 8.20 of MI-5-160 indicated that the " Input Select" switch was to be set to " Input." The switch was not removed from or verified in the " Input" position at the start of the procedure. It is possible that the switch should have been verified in the " Input" position at the start of the procedure in order to ensure correct voltages, Step 8.3.4 of MI-3-350 indicated that the health physics technician was to be informed that the monitor was back in service. The procedure, however, does not require the health physics technician to be informed when it was removed from service. This was an omission from this procedure. The technician indicated that most of the other procedures had this requirement correctly identified. It should be noted that the I&C technician informed the health physics technician when the instrument was removed from service for testing, however, it was done as a normal practic The third item identified during work observations was that the procedures permitted specific or " equivalent" instruments to be used for performing a procedure. However, the licensee had not identified which instruments are equivalent to each other; nor was the basis for equivalency verified before testing was performed. This policy does not assure that instrument sensitivity requirements will be me _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ -
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Examples found by the NRC inspector where one instrument was identified and another used were as follows: Procedure MI-5-160, Revision 1, Step 6.0, indicated a Fluke 8500A DVM was to be used. Instead, a health physics (HP) instrument was use Procedure MI-3-350, Step 6.0, indicated a Fluke 8600A Digital Multimeter was to be used. Instead, an HP instrument was use Documentation associated with ten completed maintenance activities was obtained and reviewed. The ten activities were: CIWA 028825, nitrogen pump level switch NG-ILS-3006 out of calibratio CIWA 025448, component cooling water to dry tower isolation valve low air pressure switch CC-IPS-3085B mounting repair CIWA 029024, charging pump AB spurious low suction pressure trip switch (CVC-MPMP0001AB) troubleshootin CIWA 025719, steam generator No. 1 pressure transmitter SG-IPT-1013A erratic output troubleshooting, CIWA 025913, boric acid condensate tank "B" level controller (BM-ILIC-0626) repai CIWA 022177, annunciator LO705 troubleshooting and repai CIWA 006276, SUPS IAB blown fuse F42 replacemen CIWA 023828, chill water pressure transmitter CHW-IPT-5011BS leaking vent plug replacement, CIWA 025452, containment spray flow transmitter CS-IFT-7122AS high flow indicatio CIWA 028099, boric acid condensate tank "B" level controller (BM-ILIC-0626) maintenanc The review of these completed items identified three areas of apparent weakness as follows:
The first area was a concern related to not identifying equivalent instruments. CIWA (Condition Identification Work Authorization)
028825 (item a. above) identifies a 0-415 inches water column (INWC)
instrument to be used for calibration where an 0-830 INWC was use As stated previously, this does not ensure that necessary instrument sensitivities are me Another example was seen in CIWA-025448 (item b. above) where a 0-100 psi Heise test gauge and Fluke 8600A
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DVM were identified for use as test equipment. Instead of using the identified equipment, a Helicoid 0-100 psi gauge and a Triplet meter were use *
The second weakness identified during review by the NRC inspector was that there appeared to be inconsistencies in the document review process. In CIWA 025719 (item d. above) Section D (corrective maintenance control section) was not filled out. CIWA 025913 (item e. above) identified one of the test instruments by manufacturer's name and not by its control numbe This does not permit easy traceabilit *
A third weakness was incomplete reviews as identified in CIWA 022177 (item f. above). On CIWA 022177, addendum page 11, it was indicated that plant engineering was to evaluate the acceptability of the switches used for initiating the alarm. It was not apparent that the review had been performed. No other weaknesses were noted during the
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review of these maintenance documents. These concerns will be an open item (382/8628-03) to be reviewed generically during a subsequent inspectio . Licensee Electrical Maintenance Program The NRC inspector performed an inspection of the Maintenance Program in the electrical area. Maintenance history, work item tracking forms, maintenance work requests, qualification records, document control procedures, and replacement part control records were obtained and reviewed. Selected Electrical Maintenance Organization personnel (electrical supervisors and electricians) were interviewed to determine their areas of responsibilities, functions, and qualification Three maintenance action items were witnessed to ensure that the electricians performin0 the maintenance tasks followed the appropriate maintenance procedures. All three items involved the testing of HPCI Pump AB relays. Testing was performed in accordance with the following procedures:
' ME-7-035, Revision 1, G.E. Auxiliary Relays, Models HGA11A through HGA11X ME-7-030, Revision 1 G.E. Auxiliary Relays Models HGA17A through HGA17T ME-7-033, Revision 1, G.E. Auxiliary Relay HGA14 The NRC inspector identified two areas of concern. The first concern involved test equipment. In maintenance procedure ME-7-035, Step 6.2.1, Doble equipment, or equivalent, was identified to be used to perform the testing. The technicians performing the job used Multiamp equipmen Equivalency was not determined. As stated previously, not determining equivalency or having an established equivalency list in advance fails to ensure that instrument sensitivities are acceptabl . _ _ _ . __-. --
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The second concern related to the adequacy of the procedures. Step 7.0 of maintenance procedure ME-7-033 indicated that the acceptance criterion was for the relay to pick up at rated powe The rated power was not included as part of the documentation but was determined by the technician from memory. This practice does not assure that the testing is acceptabl Another example was seen in Step 8.3.1.1 of ME-7-033, where terminals 1 and 7 were to be used for continuity verification when the relay was energize These terminals were connected to spare contact The procedure did not provide for checking contacts actually in use. This practice does not provide assurance that the relay will provide the protection intende No other concerns were identified during work observation j Procedures and other documentation associated with the following 11 i completed electrical maintenance activities were reviewed: CIWA 027805, wet cooling tower fan 6A breaker (ACC-EBTR-315A12MS)
replacemen CIWA 027484, dry cooling tower fan 58 motor (CC-EMTR-315B-3F) lug repai CIWA 006299, diesel generator feeder breaker (EBKR-3A145) spring release interlock support repai CIWA 021284, flow transmitters CC-IF-5570AS and BS hydro-test validatio CIWA 004376, static uninterruptable power supply (SUPS) 3B-5 bypass ,
transformer firing board (ID-IDEN-PSM85) temporary modificatio l CIWA 004392, SUPS 3B-S Bypass transformer firing board ;
(ID-IDEN-PSM85) testing,
' CIWA 005619, MCC 38213 and 38311 missing grommets (MCC-CABLE-GR0MS)
evaluation and repai .
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CIWA 009388, all safety related motor operated valves inspection and
' heater operation verificatio !
i CIWA 025125, reactor building purge exhaust fan E22 motor '
(HVRE-MTR-3A7AS) polarization index procedure revisio : CIWA 027249, cabinet C-24 temperature control (IC-ITC-3024) burnt wire repairs, CIWA 023669, fuel handling building flitration unit B heater
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(HVFIHPL51148) troubleshooting and repair.
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l 12 During the review of completed maintenance packages by the NRC inspector, one concern was identified. This involved document completion and review.
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In CIWAs (025125, 02749, 023669, and 006299), Section D (Corrective Maintenance Controls Section) of the first page was not completed, or was filled out incorrectl These deficiencies in themselves were not highly I significant, however, they demonstrated a weakness in the final document I
review proces Three additional items were reviewed during review of the licensee's l
electrical maintenance program as follows:
l The first item was the overcurrent testing of breakers important to safet This involved the concern that some breaker manufacturers
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have specified that alternating current (AC) overcurrent testing be
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performed only once in the lifetime of a circuit breaker, with
! subsequent testing to be done using direct current (DC). The l licensee response to their concern indicated that it was applicable to one type of circuit breaker at Waterford. The breakers in question were tested using an AC test source, filtering the output through a rectifier bank when testing the breaker. The testing
, method adequately addressed the concern.
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l The second item was the replacement of Agastat time delay relays in emergency diesel generator sequencing circuits. The licensee was questioned about the use of qualified replacement relays. Procedures governing relay replacement were reviewed and found acceptabl *
The third item was the meggering (high voltage insulation test) for long installed runs of cables. The licensee's current practice is to megger cables at the circuit breakers. This practice is acceptable when cable runs are short. When the cable runs are long, the voltage drop in the cable could prevent a valid test of insulation breakdown l resistance. The licensee committed to reviewing this concern. This
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will remain an open item (382/8628-04) to be reviewed during a subsequent inspectio . Exit Interview l
l The NRC inspector met with the NRC senior resident inspector and the l licensee representatives identified in paragraph 1 at the conclusion of I
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the inspection on November 21, 198 The NRC inspector summarized the scope and findings of the inspection.
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