|
|
| Line 1: |
Line 1: |
| {{Adams | | {{Adams |
| | number = ML20206M877 | | | number = ML20213E509 |
| | issue date = 08/20/1986 | | | issue date = 11/07/1986 |
| | title = Insp Repts 50-313/86-22 & 50-368/86-23 on 860701-31. Violations Noted:Svc Water Sys Alignment Procedure Inadequately Maintained & Radiological Posting Disobeyed | | | title = Ack Receipt of 861010 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/86-22 & 50-368/86-23.Addl Info Re Procedure 1104.29 Requested |
| | author name = Harbuck C, Hunter D, Johnson W | | | author name = Gagliardo J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Campbell G |
| | addressee affiliation = | | | addressee affiliation = ARKANSAS POWER & LIGHT CO. |
| | docket = 05000313, 05000368 | | | docket = 05000313, 05000368 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-313-86-22, 50-368-86-23, NUDOCS 8608260006 | | | document report number = NUDOCS 8611130197 |
| | package number = ML20206M866
| | | 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 = 9 | |
| }} | | }} |
|
| |
|
| Line 19: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:. | | {{#Wiki_filter:F- |
| . . .
| | - e o N0Y ?M i |
| . .
| | In Reply Refer To: |
| APPENDIX B U. S. NUCLEAR REGULATORY CONilSSION
| | Dockets: 50-313/86-22 50-368/86-23 Arkansas Power & Light Company , |
| | ATTN: Mr. Gene Campbell Vice President, Nuclear Operations P. O. Box 551 Little Rock, Arkansas 72203 . ,,' , |
| | . |
| | Gentlemen: , |
| | ..- |
| | . |
| | Thank you for your letter of October 10, 1986, in response to our letter and the attached Notice of Violation dated August 21, 1986. As a re'sult. |
|
| |
|
| ==REGION IV==
| | of our review, we find-that additional information, as discussed,with your ~ |
| NRC Inspection Report: 50-313/86-22 Licenses: DPR-51 50-368/86-23 NPF-6 Dockets: 50-313
| | Mr. Levine (during a meeting on November 5,1986) is needed. Specifically,' we continue to believe that your failure to adequately maintain Procedure 1104.29, is a violation of Technical Specification 6.8.1.a. You are required to provide a written response to this apparent violation stating: (a) the corrective steps which have been taken and the results achieved, (b) the corrective steps which will be taken to' avoid further violations, and (c) the date when full compliance will be achieved. < |
| .50-368 Licensee: Arkansas Power & Light Company (AP&L)
| | Please provide the supplemental information within 30 days of the date of this letter. |
| P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (AN0), Units 1 and 2 Inspection At: ANO Site, Russellville, Arkansas Inspection Conducted: July 1-31,.1986
| | |
| ,
| | Sincerely, Odginal Signed By J. J. E. Gagliardo, Chief Reactor Projects Branch cc: |
| Inspectors: ///D f[i/ #6 W.D.Jpson,SeniorResident Dhte'
| | J. M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O.~ Box 608 Russellville, Arkansas 72801 Arkansas Radiation Control Program Director RIV:RP8/k C:RPB' C:RPB3 MEMurphy:cs Q RHun er JEGagliardo 11/f786 11 86 11/g /86 D i I weme G |
| Reactor Inspector (pars. 1, 4, 5, 6, 8)
| | |
| _f / lb C. C. Harbuck, Resident Reactor Date Inspector (pars. 1, 2, 3, 4, 5, 6, 7, 8)
| | _-_-- _- |
| f
| | - |
| }p} 3 1. - 9i Approved: e f. R.Viunter, Reactor Projects Date '
| | . a . |
| Section B, Reactor Projects Branch
| | Arkansas Power & Light Company -2-bec to DMB (IE01) |
| 't
| | bcc distrib. by RIV: |
| , | | RPB RRI R. D. Martin, RA R&SPB Section Chief (RPB/B) D. Weiss, LFMB (AR-2015) |
| I G | | RIV DRSP RSB MIS System RSTS Operator RSB M. Murphy, RIV i |
| ?
| | o - - _ - - _ _ |
| -- ,- -
| | |
| ,- ---e , - , , s . -a
| | . . . |
| | Q |
| | . |
| | ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501)371-4000 October 10, 1986 r-----=-- 1 |
| | ' |
| | - |
| | i {'[it 6 . |
| | I LCT 2 71986 |
| | ]$i $,I OCAN198606 |
| | ,_ |
| | Mr. J. E. Gagliardo, Chief Reactor Projects Branch U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 SUBJECT: Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Response to Inspection Reports 50-313/86-22 and 50-368/86-23 |
| | |
| | ==Dear Mr. Gagliardo:== |
| | The subject response has been reviewed. Responses to the Notica of Violation are attached. |
| | |
| | Very truly yours, |
| | . |
| | J. Ted Enos, Manager Nuclear Engineering and Licensing JTE:RJS:ji Attachment ' |
| | g. [$(p MEMBEA MICOLE SOUTH UTiuTIES SYSTEM |
| | _ _ |
| | |
| | . . . |
| | O |
| | - |
| | NOTICE OF VIOLATION During an NRC inspection conducted during the period July 1-31, 1986, violations of the NRC requirements were identified. The violations involved failure to properly maintain an operating procedure and failure to obey a radiological posting. The violations and responses are listed below: |
| | A. Unit 1 Technical Specification 6.8.1.a requires, in part, that written procedures shall be established, implemented and maintained covering activities recommended in Appendix "A" of Regulatory Guide 1.33, November 1972. |
| | |
| | Paragraph C of this appendix recommends having written procedures for operation of the service water system. |
| | |
| | Operating Procedure 1104.29, " Service Water and Auxiliary Cooling System," has been established in accordance with this Technical Specification. |
| | |
| | Contrary to the above, Procedure 1104.29 was not adequately maintained by the licensee. During a system walkdown, the NRC inspectors found that five manual valves listed in Attachment A of Procedure 1104.29, |
| | " Valve Lineup for SW and ACW Systems," are not installed in the plant. |
| | |
| | These valves had been noted as not installed in January 1985, by licensee operators conducting a system alignment using Revision 16 of Procedure 1104.29, but they were still listed in Revision 22 of this procedure dated July 3, 1986. |
| | |
| | This is a Severity Level IV violation. (Supplement I.D) (313/8622-01) |
| | RESPONSE TO VIOLATION 313/8622-01 The inspector indicates these five valves were noted as not installed on the valve lineup exception sheet for Procedure 1104.29 system alignment in January 1985. He concludes that, because these remain in the current revision, the procedure has been inadequately maintained. This conclusion apparently does not consider the procedural guidance for the use of the valve lineup exception sheets. Section 9.5 of Procedure 1015.01, " Conduct of Operations," delineates requirements for valve lineups. This section requires that these exception sheets be maintained with the system lineup sheets. It specifically indicates that exceptions do not require procedure changes unless such exceptions affect required safety system alignments. |
|
| |
|
| I' -. .,
| | The subject valves were in no way affecting the service water system function and would not have required immediate ravision. This would have been evaluated by the Shift Supervisor prior to completion of plant startup. |
| V
| |
| ., --
| |
| ~
| |
| -2-Inspectior Summary Inspection Conducted July 1-31, 1986 (Report 50-313/86-22)
| |
| Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, followup on an open item, and followup on a violatio Results: Within the five areas inspected, one violation was identified (failure to adequately maintain the service water system alignment procedure, paragraph 4).
| |
|
| |
|
| Inspection Summary Inspection Conducted July 1-31, 1986 (Report 50-368/86-23)
| | The valve lineup exception sheets are not the primary means of maintaining system valve lineups in procedures. They are especially not relied on for addition or deletion of valves to the 1;neups. The review of design changes provides the primary source of information for procedure changes. Following the refueling outage ending in January 1985, valve lineup exceptions of minor significance did not result in immediate procedure changes. A major |
| Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, followup on a Licensee Event Report, and inservice hydrostatic test observatio Results: Within the five areas inspected, one violation was identified (failure to obey a radiological posting, paragraph 4).
| |
|
| |
|
| | . - . . -- . . __- _ . - . , _ - _ - . . - . .- . _ . - . .- . |
| . | | . |
| -3-DETAILS Persons Contacted
| | .. |
| *J. Levine, Director of Site Nuclear Operations R. Ashcraft, Electrical Maintenance Supervisor | |
| *B. Baker, Operations Manager
| |
| *P. Campbell, Licensing Engineer A. Cox, Operations Technical Support Supervisor G. D'Aunoy, Operations Technical Support E. Ewing, General Manager Technical Support G. Fiser, Radiochemistry Supervisor L. Gulick, Unit 2 Operations Superintendent H. Hollis, Security Coordinator D. Horton, Quality Assurance Manager
| |
| *D. Howard, Manager, Special Projects
| |
| *L. Humphrey, General Manager, Nuclear Quality D. Johnson, Licensing Engineer
| |
| *H. Jones, Manager, Plant Modifications J. Lamb, Safety and Fire Protection Coordinator
| |
| *D. Lomax, Licensing Supervisor
| |
| *R. Lane, Manager, Engineering B. Lovett, Electrical Maintenance Engineer J. McWilliams, Maintenance Manager
| |
| *J. Orlicek, Field Engineering Supervisor V. Pettus, Mechanical Maintenance Superintendent D. Provencher, Quality Engineering Supervisor
| |
| *S. Quennoz, General Manager, Plant Operations
| |
| ,P. Rogers, Plant Licensing Engineer C. Shively, Plant Engineering Superintendent R. Simmons, Planning and Scheduling Supervisor C. Taylor, Operations Technical Support Supervisor B. Terwilliger, Consultant R. Tucker, Electrical Maintenance Superintendent
| |
| ;*D. Wagner, Assistant Health Physics Superintendent
| |
| *R. Wewers, Work Control Center Manager
| |
| . | | . |
| G. Wrightam, I&C Supervisor S. Yancy, Mechanical Maintenance Supervisor
| | J |
| *C. Zimmerman, Operations Technical Support
| | |
| *Present at exit intervie The inspectors also contacted other plant personnel, including operators, technicians, and administrative personne . Followup on Previously Identified Items (Unit 1)
| | i. |
| (Closed) Violation (313/8602-01): Failure to follow a quality control procedure in seismic support inspectio ,
| |
| .
| |
| -
| |
| ,. ty-4-
| |
| -The NRC inspector verified that the specific support deficiencies identified on support 3EFW-116-H20 had either been corrected or evaluated as being adequate by the licensee. Programatically, the licensee has established an independent QA/QC organization within the plant modifications group. Independent inspection of seismic support installation, including concrete expansion anchor bolts, is assigned to this organization. In the case identified by the violation, an independent inspection was not require Further licensee corrective actions for this item were also taken in response to open item (313/8602-03), and are described below. Based on the actions'noted above and the observations and reviews noted below, this item is close (Closed) Open Item (313/8602-03): Control of seismic support installatio The NRC inspector reviewed the following recently issued licensee supplemental instructions (sis):
| |
| . SI-C-2406-2, "Non-structural Baseplate and Penetration Grout"
| |
| . SI-C-2408-1, " Concrete Expansion Anchors" These sis clarify the requirements of the associated AP&L construction Technical Specifications (TSs), C-2406 and C-2408. The NRC inspector found that they provided adequate guidance to construction craftsmen to ensure compliance with the TS The NRC inspector witnessed anchor bolt . installation and inspection for DCP 84A-2022B, specifically the placement and torquing of anchor bolts for the 2011 battery rack baseplate The NRC inspector also inspected seismic support installations for the Unit 2 EFW suction piping from the seismically qualified condensate storage tank being built. No problems were note Based on these reviews, observations, and inspections, the NRC inspector concluded that the licensee's control of seismic support installation now appears to be adequate. This item is close . Licensee Event Report (LER) Followup (Unit 2)
| |
| Through discussions with licensee personnel and review of records, the following event report was reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence has been accomplished in accordance with Technical Specification Unit 2 LER No. 86-004-00 reported an automatic reactor trip due to an inadvertent trip of a reactor coolant pump (RCP) breake P" l
| |
| , .
| |
| -5-The licensee determined that the root cause of this event was a design flaw in the RCP breaker indicating circuit on panel 2C-80 (the remote shutdown panel). The design used a full voltage light bulb (125 Vdc) for the breaker indicating lamp, which was wired in series with the breaker trip solenoid. The resistance of the light bulb was used to limit current below that which would actuate the solenoid. In this instance, the replacement light bulb was shorted. When installed in the socket its low resistance allowed a current able to actuate the solenoi The licensee completed plant change No. 86-1733 which modified the indication _ circuits of all four RCP breakers at panel 2C-80. This new design installed a step down or ballast resistor integral to the lamp socket and switched to a lower voltage light bulb. Thus, even with a bulb short circuit, the trip solenoid will not have sufficient current to actuat The licensee was identifying similar circuits and evaluating the need for any modifications. This effort was two-fold: The operation departments for both units were tasked to identify the uses of all full voltage light bulbs in their respective plants, and a consultant had been contracted to perfoirm a review of breaker circuits used at ANO to identify similar circuit designs. This effort will take some time to complet '
| |
| Based on the above corrective actions, this event report is close No violations or deviations were identifie . Operational Safety Verification (Units 1 and 2)
| |
| The NRC inspectors observed control room operations, reviewed applicable
| |
| ~ logs, and conducted discussions with control room operators. The inspectors verified the operability of selected emergency systems, reviewed tagcut records, verified proper return to service of affected components, and ensured that maintenance requests had been initiated for equipment in need of maintenance. The inspectors made spot checks to verify that the physical security plan was being implemented in accordance with the station security plan. The inspectors verified implementation of radiation protection controls during observation of plant activitie One problem was identified in this are During a routine tour of the Unit 2 reactor building, the NRC inspector observed two of four contract maintenance workers enter a posted airborne radiologically controlled area (reactor vessel head stud cleaning tent)
| |
| with no respiratory protection. The NRC inspector reported this observation to a health physics (HP) technician who verified that the posting was still authorized. The HP technician then directed the workers to remain outside the tent and notified the shift HP supervisor. The subsequuet licensee investigation (Radiological Safety Infraction / Condition '
| |
| Report) found that the airborne activity in the tent had been below the limit requiring respiratory protection. This was based on an air sample L
| |
|
| |
|
| -
| | * |
| , | | , |
| . .
| | equipment walkdown and labeling verification effort was in progress and was i |
| -6-about an hour before the incident. However, the maintenance workers did not know the results of that sample at the time. Since they had just returned from a work break and the work had been secured in the tent for a ,
| | expected to be completed prior to the next refueling outage. As part of this program, several sources of information are being utilized by the Operations Technical Support Group to revise procedures. |
| while, they assumed, based on previous experience with that job, that the area was safe. Licensee Procedure 1000.31, " Radiation Protection Manual,"
| |
| requires that all personnel comply with posted area entrance requirement This is an apparent violatio (368/8623-01)
| |
| The NRC inspectors toured accessible areas of the units to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibration. The inspectors also observed plant housekeeping and cleanliness conditions during the tour It was noted that housekeeping in Unit 2 needed improvemen Licensee management had noted a similar concern and had initiated corrective actio The NRC inspectors walked down the accessible portions of the Unit 1 service water system. The walkdown was performed using Procedure 1104.29 and Drawings M-210, M-209, and M-221. No system alignment discrepancies were identified. The NRC inspectors noted that five valves (LO-8030A, SW-609A, SW-6098, SW-607A, and SW-607B) were listed in Attachment A,
| |
| " Valve Lineup _for SW and ACW Systems," of Revision 22 of Procedure 1104.29, but the valves were not installed in the plan These valves were not shown on system drawing The NRC inspector reviewed the latest valve lineup for this system in the Unit 1 control roo This valve lineup was performed in January 1985, using Revision 16 of Procedure 1104.29. .The operators had completed Form 1015.01B,
| |
| " Valve / Breaker Lineup Exception Sheet," and attached it to the completed valve lineup sheets. _This form listed the above five valves and several others as "Does not exist." The licensee's failure to correct the service water valve lineup list in a subsequent procedure revision is an apparent violation of Technical Specification 6. (313/8622-01)
| |
| The NR'C inspector witnessed portions of the Unit 2 fuel reloading both from the reactor building refueling bridge and the spent fuel pool are No problems were note During a tour of the Unit 2 auxiliary building, upper south piping penetration room, the NRC inspector noted that the packing gland nuts were loose on valve 2BS-5614, the service air to 'B' train of the building spray system manual isolation. The licensee was informed, and the problem was corrected under Job Order 71604 These reviews and observations were conducted to verify that selected facility operations were in conformance with the requirements established under Technical Specifications, 10 CFR, and administrative procedure . Monthly Surveillance Observation (Units 1 and 2)
| |
| The NRC inspector observed the Technical Specification required quarterly surveillance testing on the Unit 1 high pressure injection pump P36C (Procedure 1104.02, Supplement III), and verified that testing was
| |
|
| |
|
| m ,
| | * |
| -
| | AP&L fails to recognize how the continued inclusion of these five valves on the valve lineup is indicative of inadequately maintaining a procedure. The i |
| w, t
| | system alignment was accomplished and correct actions for exceptions were j taken as required by the Conduct of Operations procedure. A valve lineup serves to prepare for system operation. Critical manual valve alignments are performed by the Category E valve lineup specified in Procedure 1102.01, |
| -
| |
| , . >
| |
| '
| |
| >0 ,' ]'
| |
| - , .
| |
| ,,
| |
| -7-performed in accordance with an adequate procedure, test instrumentation was< calibrated, limiting conditions for operation were met, removal and restoration of the affected componests were accomplished, test results conformed with Technical Specifications and procedure requirements, test results were reviewed by personnel other than the individual directing the test, and any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne The inspector also witnessed portions of the following test activities:
| |
| . Monthly test of charging pump 2P36A (Procedure 2104.02 Supplement 1)
| |
| . Reactor protection system channel 'B' monthly test (Procedure' 1304.38, J0 714862)
| |
| . Loop B hot leg temperature (RTD) response time testing (Unit 2)
| |
| (Procedure 4710.31)
| |
| . Quarterly source check of process radiation monitor RE-4830 (Procedure 1304.26, J0 716263)
| |
| No violations or deviations were identifie . Monthly Maintenance Observation (Units 1 and 2)
| |
| Station maintenance activities of safety-related systems and components listed below were observed to ascertain that they were conducted in accordance with approved procedures, Regulatory Guides, and industry codes or standards; and in conformance with Technical Specification The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and fire prevention controls were implemente Work requests were reviewed to determine status of outstanding jobs and to ensure that priority is assigned to safety-related equipment maintenance which may affect system performanc The following maintenance activities were observed:
| |
| . Replacement of Potter-Brumfield MOR relay for 2SV-5021-1 (Work Plan 2409.05)
| |
| . Provision of new vent path for upper south piping penetration room for high energy line break (JO 714058) (DCP 85-D-1072)
| |
| ,
| |
| . . , , . _ , y m_ , _ _ _ _ _ __ _ . . - _ . _ _ .
| |
|
| |
|
| , .. .
| | " Plant Preheatup and Precritical Checklist," and are independently verified. |
| -8-
| |
| . Battery bank replacement (JO 714021)
| |
| . Battery charger repair (2031) (JO 715042)
| |
| r
| |
| . Post-maintenance test of die'sel generator (JO 707883)
| |
| (Procedure 2306.05)
| |
| . Repair of valve 2CV-4921-1 (JO 708269) (Procedure 2402.103)
| |
| . Testing operation of valve 2CV-5650-2 using MOVATS (JO 711394)
| |
| (Procedure 1403.31) | |
| . Unit 2 emergency diesel generator 'A', 18-month electrical preventive maintenance (Procedure 2403.07) (JO 708147)
| |
| . Heat shrink insulation installation on cable splices for 'B' steam generator temperature sensors (RTDs) (DCP 85-2039, Reactor trip /EFW actuation bypass) (JO 710164)
| |
| . Electrolyte recirculation of battery 2011 following service discharge (Procedure 2403.27) (JO 2403.27)
| |
| . Calibration of pressurizer pressure transmitter 2PT-4601-3 (Procedure 2304.43)
| |
| . Replacement of low pressure safety injection system flow transmitter pipe tap and isolation valve 2SI-5091A (DCP 85-2158) (JO 711112)
| |
| No violations or deviations were identifie . Hydrostatic Test Observation (Unit 2)
| |
| The purpose of this part of the inspection was to verify that the
| |
| ~ licensee's inservice hydrostatic test procedures were adequate and that-the tests were being conducted in accordance with the procedures and i Section XI of the.ASME Cod The NRC inspector reviewed the followir.g procedures:
| |
| .2409.104 " Hydro $taticTestoftheLowPressureSafetyInjection (LPSI) System" 2409.91 " Hydrostatic Test of the Engineered Safety Features (ESF)
| |
| Pump Recircs and Train A ESF Suction Piping"
| |
| , It appeared that the procedures met the requirements of Articles IWB-5000 and IWC-5000 of Section XI of the ASME Code, and were adequate to perform the hydrostatic test The NRC inspector verified that the following items were considered:
| |
| l j
| |
|
| |
|
| w -
| | l Maintaining correct position is ensured by locking these valves. This valve l alignment was accomplished prior to heatup following the refueling outage. |
| -- ,
| |
| -
| |
| "'
| |
| \; 2 4
| |
| ~
| |
| ''
| |
| . l%. >
| |
| . >
| |
| ,
| |
| -
| |
| ,
| |
| _g_
| |
| _
| |
| t
| |
| . correct determination of the required test pressure (especially at pipe class transition points)
| |
| . duration of test required
| |
| . correct test boundary identification and valve lineup
| |
| . proper location of test pressure gages (including accounting for elevation corrections where needed)
| |
| . establishment of boundary valve leakage drain paths for overpressure protection
| |
| . adequate test equipment (pump, relief valves, test gages, hoses, etc.)
| |
|
| |
|
| . requirement for a QC inspector with an authorized nuclear inservice inspector (ANII) to perform final system walkdown at test pressure The NRC inspector reviewed the data for Procedure 2409.91 (LPSI). No problems were identifie The NRC_ inspector witnessed the performance of Procedure 2409.91, Section A, Refueling Water Tank recirculation header, Section C, 'A'
| | l The five va?ves of concern were not Category E valves. The inclusion of these valves in the valve lineup caused no performance errors and |
| Engineered Safety Features (ESF) Pump Suctions, and Section D, ESF Pump recirculation pipin Several valves were noted to have minor packing
| | ! compromised no system function. Therefore, AP&L does not concur that a |
| . leakage or seat leakage. These were identified for repair by the test engineer. No weld or piping leakage was observed. The NRC inspector concluded that these tests had been performed in accordance with the procedur No violations or deviations were identifie . Exit Interview The NRC inspectors met with Mr. J. M. Levine, Director, Site Nuclear
| |
| ' | | ' |
| Operations, and other members of the AP&L staff at the end of this inspection. At this meeting, the inspectors summarized the scope of the inspection and the finding .
| | violation of Technical Specification 6.8.1.a has occurred. |
| | |
| | , |
| | ! B. Unit 2 Technical Specification 6.11 requires, in part, that procedures |
| | , for personnel radiation protection shall be prepared and adhered to for |
| | ; all operations involving personnel radiation exposure. |
| | |
| | Licensee Procedure 1000.31, " Radiation Protection Manual," |
| | . Section 9.3.8, Paragraph C under " General Radiation Protection Rules" l requires all personnel to comply with pJsted area entrance requirements. |
| | |
| l | | l |
| '
| | ,' The pressure vessel head stud cleaning tent was posted " airborne area, respiratory protection required" for entry. |
| .
| | |
| '> 4 | | Contrary to the above, on July 9, 1986, two licensee contract i maintenance personr.al entered the tent without respiratory protection. |
| * | | |
| (
| | i j This is a Severity Level V violation. (Supplement I.D) (368/8623-01) |
| | ! |
| | l RESPONSE TO VIOLATION 368/8623-01 I |
| | ; The contractors who performed the reactor vessel stud cleaning were l counseled subsequent to the incident. They indicated that they had been |
| | , |
| | anxious to complete the job and inappropriately entered the tent before j donning respirators. They had assumed that with the machine not running, i the tent was not an airborne area. While earlier sampling had indicated no |
| | { airborne contaminates, the posting had not been removed and should not have l- been disregarded. No similar incidents occurred during the completion of l the job. Immediate actions achieved compliance. |
| | |
| | - |
| | ! |
| | ; The outage health physics controls and the contractor training were reviewed j by the Maintenance Manager and determined to be adequate. The circumstances |
| | ; of the specific incident indicate it was an isolated case involving the |
| | ! contractors providing cleaning services for reactor vessel studs. No |
| | { further action was deemed necessary. |
| | |
| | i |
| | ! |
| | i i |
| | ! |
| | : |
| | !__--..,__._._.___..._ _ ._ _. . _ _ |
| }} | | }} |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999
Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1
ML20217J4971999-10-18018 October 1999
Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes
ML20217J3871999-10-15015 October 1999
Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure
2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999
Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs
ML20217J3601999-10-15015 October 1999
Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure
2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999
Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp
ML20217D1721999-10-0808 October 1999
Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015
1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999
Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included
ML20212L0621999-10-0101 October 1999
Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability
1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999
Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria
2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999
Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000
1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999
Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3
1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999
Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative
1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999
Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data
2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999
Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827
2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999
Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR
ML20212F5031999-09-22022 September 1999
Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i)
1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999
Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments
ML20212D9961999-09-16016 September 1999
Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl
1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999
Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld
2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999
Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested
1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999
Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments
ML20211P4121999-09-0707 September 1999
Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d)
0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999
Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs
ML20211L4901999-09-0101 September 1999
Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted
ML20211J2351999-08-31031 August 1999
Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1
ML20211E6161999-08-25025 August 1999
Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days
0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999
Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999
ML20211F4181999-08-25025 August 1999
Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds
ML20211G0731999-08-19019 August 1999
Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls
1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999
Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl
ML20211C5101999-08-19019 August 1999
Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999
Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves
IR 05000368/19990111999-08-12012 August 1999
Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1
2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999
Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729
1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999
Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License
2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999
Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999
Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified
0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999
Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603
ML20210L3581999-07-29029 July 1999
Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021
1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999
Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks
ML20216D8131999-07-28028 July 1999
Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1
ML20216D3561999-07-23023 July 1999
Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1
ML20210C2191999-07-21021 July 1999
Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations
ML20209H5251999-07-15015 July 1999
Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999
Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages
0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999
Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl
ML20209E5551999-07-0808 July 1999
Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2
1999-09-09
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20062F0481990-11-19019 November 1990
Advises That SR Peterson Replacing C Poslusny as Project Manager for Facility,Effective 901105
ML20216K0001990-11-13013 November 1990
Forwards Insp Repts 50-313/90-30 & 50-368/90-30 on 900905- 1016 & Notice of Violation
IR 05000313/19900321990-11-0808 November 1990
Ack Receipt of Outlining Steps to Provide Addl Technical Support for Radiation Protection Manager.Planned Actions Acceptable as Documented in Insp Repts 50-313/90-32 & 50-368/90-32
ML20058G8471990-11-0808 November 1990
Forwards Insp Repts 50-313/90-32 & 50-368/90-32 on 900924-29.No Violations or Deviations Noted
ML20058G1631990-11-0707 November 1990
Forwards Summary of Current Status of Unimplemented Generic Safety Issues at Plant
ML20058E2881990-11-0101 November 1990
Rejects 900302 Request for Amend to Tech Specs to Revise Power Calibr Requirements for Linear Power Level & Core Protection Calculator delta-T Power & Nuclear Power Signals
ML20062D5631990-10-31031 October 1990
Forwards Insp Repts 50-313/90-37 & 50-368/90-37 on 901015-19.No Violations Noted
ML20062D5761990-10-31031 October 1990
Forwards Insp Repts 50-313/90-40 & 50-368/90-40 on 901015-19.No Violations Noted
ML20062D5511990-10-31031 October 1990
Forwards Insp Repts 50-313/90-31 & 50-368/90-31 on 901001-04.No Violations Noted
ML20059P0441990-10-16016 October 1990
Authorizes Use of Inconel 690 (I-690) as Alternate to I-600 in Steam Generator Tube Sleeves/Plugs Per 10CFR50.55a(a)(3)
ML20058A5211990-10-16016 October 1990
Forwards Insp Repts 50-313/90-38 & 50-368/90-38 on 901001- 05.Violation Considered for Escalated Enforcement Action
ML20058A0811990-10-15015 October 1990
Forwards Questions Re 900808 License Amend Request to Increase Reactor Power to 100% for Response
ML20062A5511990-10-10010 October 1990
Forwards SER Re Util 890403,13 & 0717 Responses to Station Blackout Rule.Issue of Conformance Still Open
IR 05000313/19900011990-10-0404 October 1990
Ack Receipt of 900420 & 0914 Ltrs Re Validation of Nonlicensed Operator Staffing Per Insp Repts 50-313/90-01 & 50-368/90-01
ML20059M0441990-09-26026 September 1990
Approves 900809 Request to Withhold 86-1179795-01, ANO-1 HPI Flow Rate Requirements (Ref 10CFR2.790(b)(5))
ML20059K3851990-09-14014 September 1990
Forwards Insp Repts 50-313/90-28 & 50-368/90-28 on 900827-31.No Violations or Deviations Noted.Some Weaknesses Identified in Areas of Alternate Safe Shutdown Procedure & Associated Training for Unit 2
ML20059J2431990-09-14014 September 1990
Discusses Programmed Enhancements for Generic Ltr 88-17, Loss of Dhr. Changes in Completion Schedule Should Be Submitted to NRC
ML20059J9901990-09-13013 September 1990
Forwards Info Re Generic Fundamentals Exam of Operator Licensing Written Exam to Be Administered on 901010.W/o Encl
ML20059G2951990-09-0606 September 1990
Advises That Rev 10 to Emergency Plan,Contained in ,Acceptable.Rev Consists of Changes Resulting from Reorganization,Relocation of Personnel from Little Rock Ofc & Improvements from Annual Emergency Preparedness Exercise
ML20059E8621990-08-31031 August 1990
Forwards Insp Repts 50-313/90-27 & 50-368/90-27 on 900813-17.No Citations Issued for Violation
ML20059D1551990-08-30030 August 1990
Forwards Request for Addl Info to Continue Review of 891019 Application for Amend Extending Insp Frequency of Spent Fuel Pool from Once Per 18 Months to Once Per 60 Months.Response Requested within 45 Days
ML20059E5901990-08-29029 August 1990
Forwards Summary of 900823 Quarterly Performance Meeting at Plant Re NRC Authorized Activities.Meeting Provided Better Understanding of Current Implementation Status of Program Changes at Plant.List of Attendees & Viewgraphs Encl
IR 05000313/19900161990-08-29029 August 1990
Discusses 900823 Meeting Re Unresolved Item Concerning Missed Surveillance Tests,Per Insp Repts 50-313/90-16 & 50-368/90-16.Violation of Tech Spec Requirements Noted But Not Cited Due to Listed Reasons
ML20059F3441990-08-29029 August 1990
Forwards Insp Repts 50-313/90-23 & 50-368/90-23 on 900716-20.No Violations or Deviations Noted
ML20059D6381990-08-29029 August 1990
Ack Receipt of Re Proposed Changes to Unit 1 Tech Spec 6.12.2.6(b) & Unit 2 Tech Spec 6.9.3.1.Proposed Changes Appear to Improve Quality of Semiannual Radioactive Effluent Release Repts
ML20059B8461990-08-23023 August 1990
Responds to Re Violations Noted in Insp Repts 50-313/89-33 & 50-368/89-33.Violations Remain Applicable
ML20056B4921990-08-22022 August 1990
Forwards Request for Addl Info Re Util 900618 Response to NRC Questions on Condensate Storage Tank Seismic Qualification.Response Should Be Provided within 45 Days to Facilitate Completion of NRC Effort
ML20056B4131990-08-21021 August 1990
Forwards Summary of 900718 Meeting Re Exercise Weaknesses Noted in Insp Repts 50-313/90-08 & 50-368/90-08
ML20056B4641990-08-21021 August 1990
Ack Receipt of Advising NRC of Current Status of Security Perimeter Improvements,Per Insp Repts 50-313/87-31 & 50-368/87-31.Implementation of Design Change DCP 90-2001 for Perimeter Lighting Will Be Monitored for Adequacy Later
ML20059A7011990-08-17017 August 1990
Forwards Sser Concluding That Rochester Instrument Sys Model SC-1302 Isolation Device Acceptable for Use at Plant for Interfacing SPDS W/Class IE Circuits
ML20058P2601990-08-13013 August 1990
Forwards Insp Repts 50-313/90-26 & 50-368/90-26 on 900730-0803.No Violations or Deviations Noted.Rept Does Not Include Specific Insp Followup for Any Diagnostic Evaluation Team Findings
ML20058N9741990-08-10010 August 1990
Forwards Insp Repts 50-313/90-19 & 50-368/90-19 on 900601- 0715 & Notice of Violation.Util Should Respond to Failure to Adequately Implement Surveillance Test Required by Tech Specs
IR 05000313/19900041990-08-0909 August 1990
Ack Receipt of 900611 & 0731 Ltrs Re Steps Taken to Correct Violations Noted in Insp Repts 50-313/90-04 & 50-368/90-04
ML20056A7491990-08-0707 August 1990
Forwards Safety Evaluation Accepting Licensee Fire Barrier Penetration Seal Program & Commitment to Complete 100% Review of All Tech Spec Fire Penetration Seals by 911231
ML20055J3571990-07-31031 July 1990
Forwards Review of C-E Topical Rept Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation, Per NRC Bulletin 88-011.Adequate Basis Not Provided for Meeting Pressurizer Surge Line Code Limits
ML20055J3981990-07-31031 July 1990
Discusses Util 890602 Response to Item 1.b of NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification. Sufficient Info Provided to Justify Continued Plant Operation Until Final Rept for Unit 1 Completed
ML20056A0211990-07-30030 July 1990
Ack Receipt of 890307 & s Informing NRC of Steps Taken to Correct Violation Noted in Insp Repts 50-313/88-47 & 50-368/88-47
ML20055J1201990-07-24024 July 1990
Advises That Operational Safety Team Insps 50-313/90-24 & 50-368/90-24 Scheduled at Plant Site on 900910-21
ML20055H9511990-07-23023 July 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/90-01 & 50-368/90-01
ML20055H9471990-07-20020 July 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/89-02 & 50-368/89-02
ML20058P7261990-07-19019 July 1990
Forwards Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 900606
ML20055G1801990-07-17017 July 1990
Confirms 900718 Mgt Meeting in Region IV Ofc Re Exercise Weaknesses Noted During Mar 1990 Emergency Exercise
ML20055F8011990-07-13013 July 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/89-27 & 50-368/89-27.Security Officer Training Will Be Evaluated During Future Insps
ML20055E5171990-07-0909 July 1990
Advises That 900607 Control Element Assembly Failure at Maine Yankee Not Applicable to Facility.Nrc Understands That Util Does Not Plan to Use Any old-style Control Element Assemblies in Future
ML20055D5081990-06-29029 June 1990
Forwards Insp Repts 50-313/90-18 & 50-368/90-18 on 900521-25.No Violations or Deviations Identified.Two Open Items in Areas of Procedures & Personnel Dosimetry Noted
1990-09-06
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J4971999-10-18018 October 1999
Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes
ML20217J3871999-10-15015 October 1999
Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure
ML20217J3601999-10-15015 October 1999
Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure
ML20217D1721999-10-0808 October 1999
Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015
ML20212L0621999-10-0101 October 1999
Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability
ML20212F5031999-09-22022 September 1999
Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i)
ML20212D9961999-09-16016 September 1999
Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl
ML20211L4901999-09-0101 September 1999
Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted
ML20211J2351999-08-31031 August 1999
Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1
ML20211F4181999-08-25025 August 1999
Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds
IR 05000368/19990111999-08-12012 August 1999
Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML20210L3581999-07-29029 July 1999
Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021
ML20216D8131999-07-28028 July 1999
Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1
ML20210C2191999-07-21021 July 1999
Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations
ML20209H5251999-07-15015 July 1999
Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
ML20209E5551999-07-0808 July 1999
Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2
ML20209D8521999-07-0707 July 1999
Responds to Util 990706 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required by TS 3.7.2, Auxiliary Electrical Sys. NOED Warranted & Approval Granted for Extension of Allowed Outage Time to 14 Days
ML20209A8561999-06-25025 June 1999
Refers to Investigation Rept A4-1998-042 Re Potential Falsification of Training Record by Senior Licensed Operator at Arkansas Nuclear One Facility.Nrc Concluded That Training Attendance Record Falsified
IR 05000313/19990071999-06-21021 June 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-313/99-07 & 50-368/99-07 Issued on 990514.Adequacy of Min Staffing Levels May Be Reviewed During Future Insps
ML20196D4241999-06-21021 June 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp of License SOP-43716 Issued on 990325.Believes That NRC Concerns Have Been Adequately Addressed at Present
ML20207H3551999-06-10010 June 1999
Forwards Insp Repts 50-313/99-05 & 50-368/99-05 on 990411-0529.No Violations Noted
ML20195G3481999-06-0909 June 1999
Ack Receipt of ,Transmitting Changes to Facility Emergency Plan,Rev 25,under Provisions of 10CFR50,App E, Section V
IR 05000313/19993011999-06-0909 June 1999
Discusses Arrangements for Administration of Licensing Exam During Wk of 991213,per Telcon of 990602.As Agreed,Exams Repts 50-313/99-301 & 50-368/99-301 Will Be Prepared Based on Guidelines in Rev 8 of NUREG-1021
ML20195F1631999-06-0808 June 1999
Forwards Insp Repts 50-313/99-06 & 50-368/99-06 on 990524-28.Violation Identified & Being Treated as Noncited Violation
ML20207G3111999-06-0707 June 1999
Ack Receipt of Changes to ANO EP Implementing Prcoedure 1903.010,Emergency Action Level Classification,Rev 34 PC-2, Received on 981218,under 10CFR50,App E,Section V Provisions. No Violations Identified
ML20207G7951999-06-0707 June 1999
Forwards Notice of Violation Re Investigation Rept A4-1998-042 Re Apparent Violation Involving Initialing Record to Indicate Attendance at Required Reactor Simulator Training Session Not Attended
ML20207E7131999-06-0202 June 1999
Discusses EOI 990401 Request for Alternative to Requirements of Iwl for Arkansas Nuclear One,Pursuant to 10CFR50.55a(g)(6)(ii)(B) & ASME BPV Code Section XI & Forwards Safety Evaluation Accepting Proposed Alternative
ML20207B9521999-05-26026 May 1999
Discusses GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. Staff Will Conduct Limited Survey in to Identify Sampling
ML20207B4171999-05-24024 May 1999
Forwards Corrected Cover Ltr to Insp Repts 50-313/99-07 & 50-368/99-07 Issued 990514 with Incorrect Insp Closing Date
ML20207A7771999-05-24024 May 1999
Forwards Insp Repts 50-313/98-21 & 50-368/98-21 on 981116-990406.One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy
ML20206U4541999-05-17017 May 1999
Discusses Util & Suppl Re Changes to License NPF-06,App a TSs Bases Section.Staff Offers No Objection to These Bases Changes.Affected Bases Pages,B 202, B 2-4,B 2-7,B 3/4 2-1,B 3/4 2-3 & B 3/4 6-4,encl
ML20206S4721999-05-14014 May 1999
Forwards Insp Repts 50-313/99-07 & 50-368/99-07 on 990426- 30.No Violations Noted.However,Nrc Requests That Util Provide Evaluation of Licensee Provisions to Maintain Adequate Level of Response Force Personnel on-site
ML20207B4271999-05-14014 May 1999
Corrected Ltr Forwarding Insp Repts 50-313/99-07 & 50-368/99-07 on 990426-30.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program
ML20206R4741999-05-13013 May 1999
Informs That Staff Reviewed Draft Operation Insp Rept for Farley Nuclear Station Cooling Water Pond Dam & Concurs with FERC Findings.Any Significant Changes Made Prior to Issuance of Final Rept Should Be Discussed with NRC
ML20206N7011999-05-12012 May 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created
ML20206M7581999-05-11011 May 1999
Forwards SE Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2
ML20206S1761999-05-11011 May 1999
Responds to Informing of Changes in Medical Condition & Recommending License Restriction for Senior Reactor Operator.No Change Was Determined in Current License Conditions for Individual
ML20206N4161999-05-11011 May 1999
Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-related Logic Circuits, for Plant,Units 1 & 2
ML20206S4211999-05-10010 May 1999
Forwards Insp Repts 50-313/99-04 & 50-368/99-04 on 990228- 0410.Four Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy
ML20206H1031999-05-0606 May 1999
Forwards Results of Gfes of Written Operator Licensing Exam, Administered on 990407,to Nominated Employees of Facility. Requests That Training Dept Forward Individual Answer Sheet & Results to Appropriate Individuals.Without Encl
ML20206F0611999-04-29029 April 1999
Forwards SE Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1
ML20205R6331999-04-20020 April 1999
Ack Receipt of Which Transmitted Rev 39 to ANO Industrial Security Plan,Submitted Under Provisions of 10CFR50.54(p).No NRC Approval Is Required,Since Util Determined Changes Do Not Decrease Effectiveness of Plan
ML20205P4641999-04-15015 April 1999
Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP
ML20205N7251999-04-13013 April 1999
Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl
ML20205M6881999-04-12012 April 1999
Forwards Safety Evaluation on Second 10-year Interval Inservice Insp Request Relief 96-005
ML20205L7711999-04-0909 April 1999
Forwards Insp Repts 50-313/99-03 & 50-368/99-03 on 990202- 17.No Violations Noted
ML20205K7681999-04-0606 April 1999
Forwards RAI Re risk-informed Alternative to Certain Requirements of ASME Code 11,table IWB-2500-1
ML20205G8871999-04-0202 April 1999
Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant, Units 1 & 2.Response Requested within 60 Days of Date of Ltr
1999-09-22
[Table view] |
Text
F-
- e o N0Y ?M i
In Reply Refer To:
Dockets: 50-313/86-22 50-368/86-23 Arkansas Power & Light Company ,
ATTN: Mr. Gene Campbell Vice President, Nuclear Operations P. O. Box 551 Little Rock, Arkansas 72203 . ,,' ,
.
Gentlemen: ,
..-
.
Thank you for your letter of October 10, 1986, in response to our letter and the attached Notice of Violation dated August 21, 1986. As a re'sult.
of our review, we find-that additional information, as discussed,with your ~
Mr. Levine (during a meeting on November 5,1986) is needed. Specifically,' we continue to believe that your failure to adequately maintain Procedure 1104.29, is a violation of Technical Specification 6.8.1.a. You are required to provide a written response to this apparent violation stating: (a) the corrective steps which have been taken and the results achieved, (b) the corrective steps which will be taken to' avoid further violations, and (c) the date when full compliance will be achieved. <
Please provide the supplemental information within 30 days of the date of this letter.
Sincerely, Odginal Signed By J. J. E. Gagliardo, Chief Reactor Projects Branch cc:
J. M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O.~ Box 608 Russellville, Arkansas 72801 Arkansas Radiation Control Program Director RIV:RP8/k C:RPB' C:RPB3 MEMurphy:cs Q RHun er JEGagliardo 11/f786 11 86 11/g /86 D i I weme G
_-_-- _-
-
. a .
Arkansas Power & Light Company -2-bec to DMB (IE01)
bcc distrib. by RIV:
RPB RRI R. D. Martin, RA R&SPB Section Chief (RPB/B) D. Weiss, LFMB (AR-2015)
RIV DRSP RSB MIS System RSTS Operator RSB M. Murphy, RIV i
o - - _ - - _ _
. . .
Q
.
ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501)371-4000 October 10, 1986 r-----=-- 1
'
-
i {'[it 6 .
I LCT 2 71986
]$i $,I OCAN198606
,_
Mr. J. E. Gagliardo, Chief Reactor Projects Branch U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 SUBJECT: Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Response to Inspection Reports 50-313/86-22 and 50-368/86-23
Dear Mr. Gagliardo:
The subject response has been reviewed. Responses to the Notica of Violation are attached.
Very truly yours,
.
J. Ted Enos, Manager Nuclear Engineering and Licensing JTE:RJS:ji Attachment '
g. [$(p MEMBEA MICOLE SOUTH UTiuTIES SYSTEM
_ _
. . .
O
-
NOTICE OF VIOLATION During an NRC inspection conducted during the period July 1-31, 1986, violations of the NRC requirements were identified. The violations involved failure to properly maintain an operating procedure and failure to obey a radiological posting. The violations and responses are listed below:
A. Unit 1 Technical Specification 6.8.1.a requires, in part, that written procedures shall be established, implemented and maintained covering activities recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.
Paragraph C of this appendix recommends having written procedures for operation of the service water system.
Operating Procedure 1104.29, " Service Water and Auxiliary Cooling System," has been established in accordance with this Technical Specification.
Contrary to the above, Procedure 1104.29 was not adequately maintained by the licensee. During a system walkdown, the NRC inspectors found that five manual valves listed in Attachment A of Procedure 1104.29,
" Valve Lineup for SW and ACW Systems," are not installed in the plant.
These valves had been noted as not installed in January 1985, by licensee operators conducting a system alignment using Revision 16 of Procedure 1104.29, but they were still listed in Revision 22 of this procedure dated July 3, 1986.
This is a Severity Level IV violation. (Supplement I.D) (313/8622-01)
RESPONSE TO VIOLATION 313/8622-01 The inspector indicates these five valves were noted as not installed on the valve lineup exception sheet for Procedure 1104.29 system alignment in January 1985. He concludes that, because these remain in the current revision, the procedure has been inadequately maintained. This conclusion apparently does not consider the procedural guidance for the use of the valve lineup exception sheets. Section 9.5 of Procedure 1015.01, " Conduct of Operations," delineates requirements for valve lineups. This section requires that these exception sheets be maintained with the system lineup sheets. It specifically indicates that exceptions do not require procedure changes unless such exceptions affect required safety system alignments.
The subject valves were in no way affecting the service water system function and would not have required immediate ravision. This would have been evaluated by the Shift Supervisor prior to completion of plant startup.
The valve lineup exception sheets are not the primary means of maintaining system valve lineups in procedures. They are especially not relied on for addition or deletion of valves to the 1;neups. The review of design changes provides the primary source of information for procedure changes. Following the refueling outage ending in January 1985, valve lineup exceptions of minor significance did not result in immediate procedure changes. A major
. - . . -- . . __- _ . - . , _ - _ - . . - . .- . _ . - . .- .
.
..
.
J
i.
,
equipment walkdown and labeling verification effort was in progress and was i
expected to be completed prior to the next refueling outage. As part of this program, several sources of information are being utilized by the Operations Technical Support Group to revise procedures.
AP&L fails to recognize how the continued inclusion of these five valves on the valve lineup is indicative of inadequately maintaining a procedure. The i
system alignment was accomplished and correct actions for exceptions were j taken as required by the Conduct of Operations procedure. A valve lineup serves to prepare for system operation. Critical manual valve alignments are performed by the Category E valve lineup specified in Procedure 1102.01,
" Plant Preheatup and Precritical Checklist," and are independently verified.
l Maintaining correct position is ensured by locking these valves. This valve l alignment was accomplished prior to heatup following the refueling outage.
l The five va?ves of concern were not Category E valves. The inclusion of these valves in the valve lineup caused no performance errors and
! compromised no system function. Therefore, AP&L does not concur that a
'
violation of Technical Specification 6.8.1.a has occurred.
,
! B. Unit 2 Technical Specification 6.11 requires, in part, that procedures
, for personnel radiation protection shall be prepared and adhered to for
- all operations involving personnel radiation exposure.
Licensee Procedure 1000.31, " Radiation Protection Manual,"
. Section 9.3.8, Paragraph C under " General Radiation Protection Rules" l requires all personnel to comply with pJsted area entrance requirements.
l
,' The pressure vessel head stud cleaning tent was posted " airborne area, respiratory protection required" for entry.
Contrary to the above, on July 9, 1986, two licensee contract i maintenance personr.al entered the tent without respiratory protection.
i j This is a Severity Level V violation. (Supplement I.D) (368/8623-01)
!
l RESPONSE TO VIOLATION 368/8623-01 I
- The contractors who performed the reactor vessel stud cleaning were l counseled subsequent to the incident. They indicated that they had been
,
anxious to complete the job and inappropriately entered the tent before j donning respirators. They had assumed that with the machine not running, i the tent was not an airborne area. While earlier sampling had indicated no
{ airborne contaminates, the posting had not been removed and should not have l- been disregarded. No similar incidents occurred during the completion of l the job. Immediate actions achieved compliance.
-
!
- The outage health physics controls and the contractor training were reviewed j by the Maintenance Manager and determined to be adequate. The circumstances
- of the specific incident indicate it was an isolated case involving the
! contractors providing cleaning services for reactor vessel studs. No
{ further action was deemed necessary.
i
!
i i
!
!__--..,__._._.___..._ _ ._ _. . _ _
