ML20236A195
| ML20236A195 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/07/1989 |
| From: | Callan L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Deddens J GULF STATES UTILITIES CO. |
| References | |
| EA-89-010, EA-89-10, NUDOCS 8903160465 | |
| Download: ML20236A195 (24) | |
See also: IR 05000458/1988026
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. . , , l NAR 7 1980 ' l In Reply Refer To: Docket: 50-458 License No. NPF-47 EA No. 89-10 Gulf States Utilities ATTN: Mr. James C. Deddens Senior Vice President (RBNG) P.O. Box 220 St. Francisv111e, Louisiana 70775 Gentlemen: This refers to the enforcement conference conducted in the Region IV office on February 27, 1989, with you and other members of your staff, Region IV, and Office of Nuclear Reactor Regulation personnel. This conference involved the findings of the NRC inspection conducted December 1-31, 1988 (NRC Inspection Report 50-458/88-26 dated February 7,1989). The subjects discussed at this meeting are described in the enclosed Meeting Summary. In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10. Code of Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Room. Should you have any questions concerning this matter, we will be pleased to discuss them with you. hEginbi[;ned By ' Dwight D. Chamberinin L. J. Callan, Director Division of Reactor Projects Enclosure: Meeting Summary cc w/ enclosure: Gulf States Utilities ATTN: J. E. Booker, Manager- River Bend Oversight l i P.O. Box 2951 Beaumont, Texas 77704 / . [[k RIV: .DRP/C D:DRP / jVj ( lGL4 stable orn LJCallan 3/(f /89 3/ /89 3/g/89 y ((g \\ 1 , 8903160465 890307 ~ PDR ADOCK 0Su00458 O PDC
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' < , 2 T Gulf States Utilities TATTN:' Les. England Director Nuclear. Licensing ' . RBNG. i , P.O. Box'220 ' 'St. Francisville, Louisiana '70775' ,l . , ' Louisia'a State University,. . , n Government Documents Department. ' Louisiana Radiation Control Program' Director bectoDMB(IE45) q. , .4 bec distrib'. by RIV: .. ~ RRI A I DRP . SectionChief(DRP/C)- R.~D.: Martin..RA Lisa Shea, RM/ALF MIS System RPB-DRSS RSTS Operator ' Project Engineer, DRP/C RIV File W. Paulson, NRR Project Manager;(MS: 13-D-18)' .DRS- c. $ o ., [, . < ' s L n
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,. , . .. . . . . . MEETING SUtNARY , , Licensee:- Gulf States Utilities I " Facility: River Bend Station License No.: NPF-47 , ' Docket No.: 50-458 Subject: Enforcement Conference Concerning NRC Inspection Findings (NRCInspectionReport 50-458/88-26) l On February 27, 1989, an enforcement conference was. held in the Region IV office .) with representatives of Gulf States Utilities and NRC staff to discuss the , findings documented in NRC Inspection Report 50-458/88-26 dated February 7,1989. l The attendance list is attached. , The NRC discussed its concern regarding two apparent violations of NRC j requirements. The first issue discussed involved very high radiation doors ! that were left unsecured on eight occasions during an 18-month period. The i second issue involved a failure to reinstall allignment pins on the base of the RCIC turbine that were required to maintain seismic qualification. 'The - licensee discussed the sequence of events. the safety significance of the issues and corrective actions taken. Handouts prepared by GSU for the meeting ' are attached. . I Attachments: J '1. Attendance List
2. GSUPresentation(NRCdistribution) . - ) e 1 > 4 - , ) _ } 1
- _ - _ . .. - - ' bc ..th ' , [. .. .;; '.- LL '- ATTENDANCE LIST , . L Attendance at the GSU/NRC enforcement conference on February 27, 1989, at the D ', . NRC: Region IV office: . GSU J. C. Deddens, Senior Vice President J. E. Booker, Manager - River Bend Oversight L. A. England Director Nuclear Licensing T. F. Plunkett, Plant Manager i J. R. Hamilton, Director, Design Engineering M. F. Sankovich, Manager, Engineering ! E. M. Cargill, Director, Radiological Programs l NRC ! ! G. F. Sanborn, Enforcement Officer , L. J. Callan, Director,. Division of Reactor Projects
R. L. Bangart, Director, Division Radiation Safety & Safeguards . R. E. Hall, Deputy Director, Division of Radiation Safety & Safeguards W. A. Paulson, NRR Project Manager, Project Directorate IV , B. Murray, Chief, Reactor Project Branch - R. E. Baer, Chief. Facilities Radiation Protection Section G. L. Constable, Chief, Project Section C O O I e k 4 - _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _
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i AGENDA ' FEBRUARY 27, 1.989 .. ENFORCEMENT CONFERENCE o- Introductions / Overview. L. A. England l Director-Nuclear Licensing i i ~! o Remarks J. C. Deddens Senior Vice President River Bend Nuclear Group . o Review of RCIC Turbine Dowel Pin M. F. Sankovich Root'cause investigation Manager-Engineering Corrective actions o Review of Very High Radiation T. F. Plunkett Doors Plant Manager Root cause investigation Corrective actions o NRL' Questions / Comments Region IV Personnel o Closing Remarks J. C. Deddens Senior Vice President River Bend Nuclear Group - . . _ _ _ _ _ _ _ _ _ _ _ . . _ _ . . __ __ _
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, , .. . i 1 , , . i. ENFORCEMENT CONFERENCE . + CONTROL OF VERY HIGH RADIATION AREAS i
I FEBRUARY 27, 1989 . l f
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o . _ _ . . _ _ _ _ _ _ _ _ _ _ - - _ _ _ --_ ' - . - . . ' ' RIVER BEND RADTmnrm'AL CDmHS - ., i ' . Radiation Areas - RWP Required For Entry - Posted . High Radiation Areas - >100 mrem /Hr - 1000 mrem /Hr Barricade and Post at River Bend Station nest are - maintained locked. Very High Radiation Areas - >1000 mrem /Hr must be locked or i attended at all times. Very High Radiation Exclusion Areas - Potential lethal doses or exceed NRC limits in a ' short time - e.g. Drywell, j and Fuel Transfer Area. ' Iocked and requires permission of Director - Radiological Programs or designee to enter. ' GET and GET requalification emphasizes very high radiation area door controls for all personnel. nntw. Iiptiss .. River Bend Admin. NRC Whole Body 1 Rem /Qtr 3 Ran/Qtr 4 Rem / Year 12 Rem / Year ' Extranity 12.5 Ran/Qtr 18.75 Ren/Qtr Skin of Whole Body 5 Ran/Qtr 7.5 Rem /Qtr 1 _ _ _ _ _ _ _ _ _ - _ - _
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VERY HTr3T RADIATICEI DOCBS l . l l ' ' Fifty-six (56) doors umst be controlled as very high radiat. ton areas. l l 1 l TYPFS Fire Doors - . Wire Cage Doors "-
One key type for all very high radiation areas - Lori high security l tumblers. i Shift Supervisor sul C.O.F. are issued a key for emergencies only, Radiation Protection maintain seven (7) keys for their use. Very high radiation area controls prior to June 1987: 1. Signs on doors indicating that doors . nust be locked or attended. 2. Personnel sign out very high radiation keys from Radiation Protection,' memo placed in sign out book stating their responsibilities. 3. (a) Radiation Protection Technicians check very high radiation doors daily. ' (b) Security Officers check very high radiation doors two (2) times per day. .. (c) Eighteen (18) month period 91,980 individual door - checks. 4. Maintenance quarterly PM to lubricate and inspect doors for operability. 2 _ _ - _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ . _ __ ____- _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _
n =--.----- - o .. . , . . . . . . ., . HISTGN & QERELTIVE ACITGIS e . i June 26, 1987 Radiation Protection issues mano to RP Technicians, reninding them that all personnel issued very high radiation keys nust read memo outlining responsibilities. Sept. 27, 1987 Radwaste door open and unattended. RP Technician thought to have been in roca last. The Contract Technician terminated employment with G.S.U. on 9/28/87 without notice. March 26, 1988 Door not locked. Door handle was bent and made latching difficult. All very high radiation doors were checked for operability problens and problems corrected. June 22, 1988 South door to heater bay open. Disciplinary action taken against the individual responsible. Also subject discussed in safety meeting via Safety Bulletin. 3 l - _ _ _ _ _ _ - _ - _ _ _ - _ _ _ - _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ - - _ - . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - _ _ - _ _ - - _ - _ - - _ . _ _ _ _ _ - _ - -
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.9 - . ,. , <. ., n 4 '- l . , HISTGtY T GItitECTIVE ACTIGIS (GMT'D) . - , , .. Oct. 22, 1988 Watertight door not secured. Individual was not.' , familiar with locking device, 'and.' lock was ' difficult to operate. (1). ' Safety bulletin dedicated to high radiation ' area doors. (2) Check e and a regnalification lesson plans to de& amine adequacy of instructions pertaining to high radiation door key control. ! (3) Modify the key. issuance log to provide separate log for high radiation area key control. < (4) Provide a listing of all high radiation. area doors to all deltnents. - (5) Responsible indivM=1 was trained in- the p. c r use of high radiation area doors. ! (6) Sign has been placed at watertight door with l operating instructions. i . i ! Dec. 12, 1988 '1he Plant Manager implemented a new program for the control of very high radiation doors.
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- ' " - .. . , l .: - l MEMORANDUM l ' 1 . T0: W. J. Beck, E. M. Cargill, D. R. Derbonne, P. D. Graham, K. C. Hodges, V. J. Normand ' FROM: T. F. Plunkett $ / December 7, 1988 TFP-251-88 SUBJ: Control of Very High Radiation Doors Last week, two very high radiation area doors were found closed'but ' not locked. This is a serious matter requiring the following corrective , actions: ! 2
Keys to very high radiation areas will only be issued to Radiation Protection personnel (except for the two keys issued to Operations { for emergency use only). Radiation Protection personnel will be responsible for unlocking and l
ocking the door. Radiation Protection personnel will log the opening and locking of the door. They will obtain a verification sianature that the door is locked from one of the individuals j entering the area. Daily, very high radiation area door che::ks will be made by both
Radiation Protection and Security. . Radiation Protection will monthly do an operability check of each
very high radiation area door. Problems with the doors will be corrected on a priority basis.
Each of you are requested to have these corrective actions discussed with the employees under your direction by 12/31/88. Please document the compl etion of these employee discussions in a memorandum to me. , , ' These corrective actions will be in place starting with the day shift (0600) on Monday, December 12, 1988. Please have the necessary procedures TCN'd to reflect the corrective actions by this date.. TFP/jkp cc: J. C. Deddens J. E. Booker T. C. Crcuse W. H. Odell ' M. F. Sankovich 5 K. E. Suhrke _ - _ -
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. . . IOOT CAUSE ANALYSIS l- .
- Personnel Training Did Not Correct 'Ihe Problem
- ' Specific' Individual Accountabi3ity Is Required
Independent Verification Is An Iriportant Preventive Measure
i 1 Condition Report Trending Would Have Alerted River Bend Earlier
'Ib Seriousness Of Events . i . . 6
,_ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ __ .. . _ - . _ _ _ _ _ _ _ _ _ _ _ l m ,, . . j l ,v: , , , , ., .- . . ., . ! .. PERSGtEL SAFIEY SIGNIFICNKE . 1. The requirement to lock very high radiation areas is designed to prevent excessive exposures of personnel. As is apparent by the TLD results since the start-up of River Bend Station, there were . no unexpected personnel exposures. 2. The majority of the doors that were not secure were closed, giving the'aparance of Security. Therefore an individual would have to be' looking for a very high radiation area to enter in' order to discover an open one. l 3. Additionally,.very high radiation areas that might be considered , lethal are controlled as very high radiation exclusion-areas and require the approval of the Director-Radiological Programs for entry. 4. No doors open and unattended since implementation of the present Program. 7 _ - _ _ _ _ _
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, ,. . . , ,,f I :' _ . ': l' I , . Topics for Discussion LER 88-027 e- Installation of'the RCIC Turbine e Impact of delayed corrective action on plant operability, o Effectiveness of the River Bend . Configuration Management Program. . . 1 - . . . -
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. , . ., . . INSTALLATION OF RCIC TURBINE WITHOUT DOWEL PINS Reported Condition e GSU confinned on 12-19-88 that: Pedestal Bolts were not Lockwired Oil Piping Supports were Missing Tapered Dowels were Missing e Declared Inoperable 12-19-88 'e Restored to Operable Status 12-24-88 . . l 2 - __ - - _ - _ _ - _ _ - - _ - _ - - _ - _ - _ _ _ _ _ . __
l , l . .. . .. l. - . . - 1 ' 1 l , . ' 1 I ! ! i i Investigation . e GSU was in the process of reviewing and prioritizing MR's in the backlog when the deficiency was identified, e In addition to the normal effort GSU responded to: NRC - Inspection Report 88-01 and committed to review all MR's related to CR's by 12-31-88. 1 INPO - Committed to reduction in Backl.og by 12-31-88. . i ! 3 .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - - _ _ _ - _ _ _ _ _ - - _ _ - _
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, . . .. . . . , l i ' . l l . . i Root Cause i e Oversight i Contributing Factors e Pre-fuel load punch list was on a building basis which was less detailed than system lists. . I e The impact, of the missing dowel pins on operability was l overlooked. l e Due to large numbers of MR's in the backlog it did not surface quickly. i ' . 4 ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _
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, ~. ~. . , ., . . . N0" CMSEI E E RE;ATED D 'S AS OF FEBRUARY 14, 1989 1,800 - 1 - 1,700 - l 1, b 0 0 " o- APS CAND ( 90) i . 1,500 - - ,.APPROYED (723) 1,400 - 1, 300 - - 1,200 - m - 1,100 gpe- -g 2~ 1, 0 0 0 - $ 9002 5 APPROVED - $ 800 - 3 '
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^ $ b80 J* * * * " * * ' * * *[- o - 500- , oc APPROVED PROJECT SCHEDULE (APS) CANDIDATES " 400. m - - u - o ~ 300 - 8 a --- 200- ? ' ~ o - i o m 100 - g; g 5 0' , , , , , , , , , , , , , , , , , 0 N D J F M A M J J A S 0 N D J F 19 8 7 l - - -- - -- -- - ----- -19 8 8 - -- -- - -- - -- -- - --- ----- -- - l 19 8 9 5 <
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,. . . ,, l , l ' . l i Safety Assessment ! . ! 1 e Pre-installation generic seismic tests on RCIC turbine , greater than GSU requirements. ! I l i Properly aligned even though dowels were missing. e ! e Safeguard analysis showed that bolting forces were adequate for OBE and SSE conditions. i i I e RCIC system is a back-up to a back-up and is not actually i required since RB5 has ADS, ! ) 1 e Likelihood of a seismic event and a control rod drop accident 1 (CRDA) without off-site power and HPCS inoperable is approximately 10"7 Actually operated successfully twice in last 4 months. e . i 7 L_ _ _ __________________.___ _ _ _ _ _ _ _ _ j
__ __ _ -___.___ ___ ___ _ _ , - - . ,- . ;. _ . . ., ) . , ) ' . q Improvements in GSU MR Program 1 e Evaluation of prioritization process: , Projectreview Screening Committee Work Scope Comittee - ILS for all MR's 1 e Cancelled MR's did not include those in the following categories (unless individually evaluated): l a) Previously authorized MR's b) Design completed MR c MR initiated after 9/1/87 d MR's on Plant Managers' Priority List e MR's closing out PMR's f) MR's closing out CR's gJ ISEG recommended MR's h)i MR's closing out QAFR's 1 ConnitmentMR's(TRAC) j) Radiological sponsored MR's k-) Industrial-Safety MR's 1 Fire Protection MR's m Security MR's n FRC action Mt's o 15-255 MR's ! l e Addition / Cancellation Form initiated in August 1988. ! e Cancelled MR's are returned to originator and those related to CR's are sent to QA. I l i l i 8 _ _ _ - _ - _ - _ _ _ - _ _ _ _
1 , To: J. R. HAMILTON Modif cotlin Request # l ". FROM:
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DATE: i TProporer) l JUSBRCABON AND CANCELLABON FORM ! l - l l Fill out Section i for Justificotton of MR only: Fill out Section I & ll for Cancellation of MR l . l Use continuation pages as necessary. ._ _ _ _ _ _C_H_E C_K_ O_N_E_:_ _ _ _ _ _ _ _ _ _- _ _ _ _ _ _O_ _C_A_N_C_E_LL_A_B_ _O_N_ _. _ _ _ _ _ __ _ _ - _ _ _ _ _ - ' SECTION I 1) What is the Intent of the Modiflection and how would it improw the system or st'ucturef l . 2) What are the consequences if the Modification is not completed? l 3) pn n is the Modificotton necessory for plant operation? If ps, Explain. 4) yes no Will the plant have to be shutdown or be prevented from storting up if the O O Modification is not implemented? If >es, explain. . 5) ps no Would a plant or system outoge be required to implement the MRf O O If We, explain. 6) is this Modification related to oction committed in any of the following: ws ,n o. Document # Verffled by DCC O O we " O O en O O omm . _ _ _ _ _ --- _ - _ _ _ _ _ _ Pc_e_ .P_ a: _ae"> * L _ _ - _ _ _ --- _ _- _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . SEC110N ll 7) What is the pstificotton for concelling this MRT Speelfy superceding documents. 8) If Correctiw Action for CR's or other items referenced abow is not neccescry , why not? Explain. ) l l 9) If Corrective Action is still necessary, what document will implement corrective actiont l Exploln. l l ~ l 10) If TRAC ltems were referenced abow: I Attach a copy of the updated TRAC datobuse item showing the revised response. 11) ym no Was the MR " Authorized" by the Work Scope Committee? O O l 12) ps no if Modificotton is concelled,would any Calculations, Setpoints, LCN's, LCR's.GE O O documents, Spore Ports, Q-List ECSIS, etc.need to be revised? Specify documents. o . _ _ - - _ _ - - _ _ _ - _ _ _ _ - _ _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ - _ - - _ - - - _ _ _ _ - - - _ - - - _ _ - _ _ _ - _ - _ - - - - - - - - _ . SIGNATURES REQUIRED FOR CANCELLATIONS ONLY: DE SUPV WSC/PM ltem 12 wrified by DE os COMPLETED DCC j
- Attach this to the front of the Original MR.**
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. . , . . - - j - -. .. . . . . , ! , ! , I- Sununary of Corrective Action e Turbine Installation Completed j ! e Dowels, lock wire and pipe clamp installed 12-24-88. l - e Virtually all backlog MR's scheduled All open MR's requiring field work that were not prioritized werescreened(12/88)noneimpactoperability. All incomp(lete construction modifications (IS-255 items) were screened 12/88). Unscheduled MR backlog reduced from approximately 1200 in January 1988 to approximately 50 by March 1989. e Safety implications of RCIC installation insignifice.nt. ! . e Comprehensive review of configuration management program at River Bend shows it is thorough and effective. ~ . 1 . 10 t .
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