ML20058A219

Forwards Summary of 900917 Mgt Meeting at Licensee Site Re Activities Conducted Under License NPF-47

ML20058A219
Person / Time
Site:	River Bend
Issue date:	10/11/1990
From:	Gwynn T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Deddens J GULF STATES UTILITIES CO.
References
NUDOCS 9010250336
Download: ML20058A219 (53)

Text

{{#Wiki_filter:_ _ _ h -s o OCT 1 I E k [ In Reply Refer To: [ Docket: 50-458 l" Gulf States Utilities ATTN: Janes C. Deddens Senior Vice President (RBNG) P.O. Box 220 St. Francisville, Louisiana 70775 Gentlemen: This refers to the management meeting conducted at your request in the River Bend Station (RBS) main administration building on September 17, 1990. This neeting related to activities' authorized by NRC License No. NPF-47 for the RBS. The purpose of this meeting was to provide NRC management with an overview of the work planned for the refueling outage that began on -September 28, 1990. The subjects discussed at this meeting are described in the enclosed Neeting Summary.. This meeting was attended by those on the attached Attendance List. It is our opinion that this meeting was beneficial and has provided a better understanding of the efforts that GSU had undertaken to address identified issues and help mitigate any future concerns. However, the NRC staff remains very concerned with the potential for increased radiation exposure principally as a result of Cobalt-60 that is accumulating in your reactor systems. Althcugh your radiation control and ALARA practices are good, diligent efforts to reduce this source term appear to be warranted. We acknowledge your commitment to brief the NRC staff on the progress 'of your source term reduction effort during the first quarter of 1991. In addition, a matter that was not on the agenda was discussed due to increased NRC staff concern about the loss of experience on your staff as a result of personnel turnover. 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 l discuss them with you. Sincerely, - h Thomas % By: P. Gwynn 3 @Q Samuel J. Collins, Director

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Meeting Sunnary w/ attachments cc w/ enclosure: Gulf States Utilities ATTN:.J. E. Booker, Manager-l Nuclear Industry Relations + P.O. Box 2951 ~ Beaumont Texas 77704 i Bish'op, Cook, Purcell & Reynolds ATTN: Mark Wetterhahn, Esq. 1401 L Street, N.W. Washington, D.C. 20005. Gulf States Utilities . ATTN:. Les England Director Nuclear Licensing P.O.: Box 220 ] St. Francisville, Louisiana 70775 ~ - Mr. J.- David McNeill, III J William G. Davis, Esq. Department of Justice Attorney General's Office P.O. Box 94095 Baton Rouge,' Louisiana 70804-9095 H. Anne'Plettinger 3456 Villa Rose Drive Baton Rouge, Louisiana 70806 ' President of West Feliciana . Police Jury I P.O. Box 1921 St. Francisville, Louisiana 70775 'i Cajun Electric: Power Coop. Inc. t ATTH: Philip _G.; Harris <10719 Airline Highway P.O. Box 15540 Baton Rouge, Louisiana 70895 i Department of Environmental Quality ATTN: < William.H. Spell, Administrator Radiation Protection Division 'P.O. Box 14690-Baton Rouge', Louisiana 70898 'i

sw;. 2es. i " Gulf States Utilities j l U.S. Nuclear Regulatory Commission <t

ATTN

Resident Inspector P.O. Box 1051 -t St. Francisville, Louisiana 70775' l U.S. Nuclear Regulatory Cornission l ATTN: Regional Administrator, Region IV 611 Ryan Plaza Drive. Suite 1000 -!4 - Arlington. Texas 76011 bec to DMB'(IE45) r bec distrib. by RIV: R.-D. Martin

• Resident Inspector DRP
• SectionChief(DRP/C) i Lisa Shea, RM/ALF
• MIS System DRSS-FRPS
• RSTS Operator Project Engineer'(DRP/C)
• RIV File i

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• Senior Resident Inspector,: Cooper-Senior Resident Inspector,, fort Calhoun i

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~* i MEETING SUt'KARY L . Licensee: Gulf States Utilities Facility: River Bend Station License No.: NPF-47 Docket No.: 50-458

Subject:

MANAGEMENT MEETING TO PROVIDE AN OVERVIEW OF THE WORK PLANNED FOR REFUELING OUTAGE NO. 3 (RF-3) AND TO DISCUSS Tile STATUS OF OTHER AREAS OF INTEREST T On September 17, 1990, GSU personnel met with representatives of NRC Region IV- ~ in St. Francisville, Louisiana, to provide an overview of the work planned for RF-3 which began on September 28, 1990. The presentation included discussions 5 on preoutage planning, i.e., lessons learned from previous outages; the naintenance work order plan and work control; source term and associated corrective actions; and clearance program improvements. The licensee's presentation addressed the major activities that were scheduled for RF-3. Also discussed were the short-and long-term corrective actions that have been or will be taken to address identified issues and help mitigate any future concerns. A copy of the licensee's presentation material is attached. Attachments: 1. Attendance List 2. Licensee Presentation Material (NRC distribution only): Meeting Agenda RDS Refueling Outage Goals RF-3 Outage Handbook (cover only) RF-3 Planning Presentation RF-3 Maintenence Improvements RF-3 Man-Rem Projects (including figures) RBS Source Term Reduction - Loag-term Action items Protective lagging

ATTENDANCE LIST Attendance at the management meeting between GSV and NRC on September 17, 1990, in the RBS main administration building: GSU J. Deddens, Senior Vice President, River Bend Nuclear Group P. Graham, Plant Manager W. O' Dell, Manager, Oversight K. Suhrke, General Manager, Engineering and Administration D. Perbonne, Assistant Plant Manager, Maintenance P. Freehill, Assistant Plant Manager, Outage Management J. Schippert, Assistant Plant Manager, Operations, Radwaste and Chemistry E. Cargill, Director, Radiological Program L. England, Director, Nuclear Licensing R. Gaylor, Director, Computer Systems J. llamilton, Director, Design Engineering W. Beck, Supervisor, B0P Design C. Fantacci, Supervisor, Radiological Engineering D. Lorfing. Supervisor, Nuclear Licensing , Cajun Electric Power Coop. Inc. L. Johnson, Site Representative NRC R. Martin, Regional Administrator B. Boger, Assistant Director for Region IV and V Reactors, NRR T. Gwynn Deputy Director, Division of Reactor Projects (DRP) J. Jaudon, Deputy Director, Division of Reactor Safety i G. Constable. Chief, Project Section C, DRP B. Murray, Chief, RP&EPS, Division of Radiation Safety and Safeguards C. Abbate, RBS Project Manager, Project Directorate IV-1, Office of Nuclear ReactorRegulation(NRR) E. Ford, Senior Resident Inspector, RBS, DRP ) i 1 l

l I,i, j River Bend Station i Refueling Outage Goals M e:Au ess a.e G.,. w.4,.',k /^I ll J Measure (.q A of Stctenn = l %p I 1.l M*asu'e I _ Of buC04*$$ '90Ab e y ww.wg. o.a..,e .. _T_10% \\ "'b'*C"** 1soAL: w w.sii T M L J "T 5 30% x l - +ooAL: w e t. "t=,, s 0 DAYS s 0 s e, s_ ADRAL:j, w 4R f } f.i .i ~ Measure \\ _ "'..b'*'2??._ _4 _ n w.,.,; x < 10% \\, if Suct ess -u _m - m0 'GDAbM ay, ' ..[ I [1 ' ' 5 ^ e_ n of huccess %/ f4QRow s# @ ; C f7 ff[ 1 3 .) y ~ i e,s,m, <, ss<3 l oi

es-m-sa +,-A-.s-u.a g-,m.am-m-m.s a w-aau.as ,e ,,,s -w-_-,_ ---y o \\ 1.. ~ 5 t i! GULF STATES UTILITIES COMPANY RIVER BEND STATION F O e [g I 5_: l H l l RF-3 OUTAGE HANDBOOK i

i l; -.s j I CLEARANCE RECEIPT RECEIPT NUMBER I l-1 I POSSESSION OF THIS RECEIPT BY AN AU- ' THORIZED CLEARANCE HOLDER INDICATES THAT THE REFERRENCED CLEARANCE HAS 3EEN PROPERLY PLACED, CHECKED, AND

AOCEPTED, ADEQUATE PROTECTION HAS BEEN PRO-VIDED TO PREVENT PERSONNEL INJURY OR EQUlPi4ENT DAMAGE WITHIN THE CLEAR-ANCE BOUNDARY, i

CLEARANCE NC; 'NORR DOCUME. oi. C: l \\r .~ i D *l P, C. T.J. [ ? 'T; - momeme e. - c % og 4 har eg 8 'I f 1 1, g { i t-1 .J._ "~~~65ii6T dusubXfi-~~ QSUN002199 90(Junel

, 1-AGENDA Third Refueling Outage Preparation Meeting with NRC Management Scptember 17, 1990 TSC Conference Room - 1:30 PM Opening Remarks Jim Deddens/Phil Graham Third Refueling Outage Planning Pete Freeh111 MWO Work Plan and Work Control Don Derbonne Source Term Short Term Corrective Action Chuck Fantacci Lessons Learned from Trip to Japan John Hamilton Long Term Corrective Action Wally Beck Clearance Program Improvements Joe Schippert Dertonstration of Clearance System Ron Gaylor i w =)

i b-4 RF-3 PLANNING PRESENTATION for 4 NUCLEAR REGULATORY COMMISSION September 17, 1990 i e I l t e Critical and Near Critical Path Activity i i e L-II Schedule i i e Task Sunraary i e Contracted Tasks 8-Service Water Tasks e Application Of Lessons Learned e Goals e Backup Systems Contingency Review

CRITICAL PATH e Shutdown 0000 September 29, 1990 Synchronize 2400 November 25, 1990 0 Local Leak Rate Tests - LLRT e 198 Valves e MSIV e Feedwater Check Valves e 64 Procedures e Contingency Repairs Plans NEAR CRITICAL PATH 9 ECCS Outages j -i e Diesel Generator l e RHR i e Service Water ECCS Tests Scheduled at Outage End o 0 Reactor Servicing e Full Shuffle o CRD Replacement e Control Rod Replacement e In Service' Inspection e Fuel Sipping 9 Turbine Inspection s High Pressure Section e TCV, TSV, ICV e Auxiliaries

i t i L-II SCHEDULE i I 9 LLRT r e MSIV LLRT & Repair 9 RPV O Primary Containment t 9 Diesel Generator & Service Water e ECCS e-Shutdown Cooling e Level Control e Containment Cooling [ t System & Subsystem Outages l j' 1 l l

i TASK

SUMMARY

I i i l 9 e 1200 MWO - Maintenance Work Orders e 2800 PM. - Preventative Maintenance' Tasks e 38 MR - Modifications e 342 STP - Surveillance Test Procedures e 832 ISI - Inservice Inspection Tasks e 108 Erosion Examinations e 21 Signature Tests h e 5000 Total Scheduled Tasks l l 1 i

-? 4 o CONTRACTED TASKS .1 General Maintenance - SWEC I Reactor Servicing - GE l Turbine Inspection - Bechtel ' Diesel Generator Inspection - Cooper Insulation - ANCO LLRT - SWEC ISI - Rockwell-EBASCO Contingency Service Contractors

1 SERVICE WATER TASKS i 1 l 8 13 Spool Replacements 9 14 Heat Exchange Inspections 9 Standby Cooling Tower Inspection 9 Normal Cooling Tower Basin & Flume Cleaning 9 Valve Inspection 9 Drywell Cooling Coil Replacement e Chemical Cleaning Preparation Modifications 4

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LESSONS LEARNED 7 f i e Safety Tagging 9 Contractor Work Control l 0 ECCS Test at Outage End 9 SRV, Drywell Cooling Coil Carry-In e Radiation Level Reductions 9 Fuel Pool Assist Cooling Mode L L 9 MWO Field Walkdown l j e Improved L-III Schedule Reviews e Early GMC' Mobilization S. One Stop Check-In Facility 9 -MR and MWO Scope Control

GOALS 1 SAFETY l 0 4 575 Man Rem e' O Lost Time Accidents e 4 7 Recordable Injuries e O Near Miss Accident 0 4 3 ESF Actuations e O Stop Work Orders TASK e b Schedule Negativity e 4 10 Emergent MR (Ex Safety Items) 0 4 30% Emergent MWO e 4 10% PM Scope Growth e f 10% Preoutage MWO Growth e O Preoutage MR Growth EMERGENT WORK CRITERIA e LCO-Limiting Conditions for Operation e Required for Plant Restart e Task requires a plant shutdown and significant availability or capacity factor threat e Required to fulfill a consnitment

?., SAFETY REVIEW 9 Shutdown Cooling 9 Service Water 9 Preferred Transformer Availability 9 Diesel Generator Availability 9 Potential To Drain RPV 9 Core Alterations 9 Fuel Movement 9 Containment

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'.s i ~ .s IW-3 N DWIora m RB PIE N X m e M C R E cit 3 T G I c Goal Actual (9/11/90) I&C 100 109 Mach 25 79 Elect 25 57 i 'IUIAL (GSU) 150 245 + Other 66 GRAND TCSL 311 . Started 7/02/90 - 680 9/12/90 - 311 SDWDC RENIRBERE 14 I&C Tech's 2 Forenan 14 Mechanics-2 Foreman 6 Electricians 1 Foreman 9

'o.' i v MP-3 MIN M OUKE N MINGBOWE3 PUGOEDC March 1990 outage planners cr. site Developed detailed job plans 1- ? Prepared IMP's-and, tagouts Parts identified and staged IJMlL III N2 REVI3Bt GRDUP Ensured correct logic Reviewed manheur estimates Man leniwi schedules MO granmes auxp Verified parts Checked tools Subnitted.tagouts and RWP's Prepared insulation rernoval and scaffolding roquest -l l l i, l l' i

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- APPROX MWO'S FOR RF-3 / s# I W 900- -x-11W0 RF-3 SCOPE APPROYED 2' # # I s / 027 a 000- -,.. MWO PLAtNED .r. g / v3 l ) ~ 700- -e-11WO PARTS STAGED en. l g '= 7 r 600-j )r4 500-t' / 4 A 400- /-r.e / / 300- / , * -/ r. 200"; E.'(("']'- M 100- +- 0^ t iie i i e 4 1 i i i i i-6 i i i 6 i i i 6 ii i o e i i 1/1 4/1 5/1 6/1 7/1 0/1 9/1 WEEKS i l

N p; =. i + IF-3 E DfB N OKE N ID E R E FI' 1 G EC 1 0 06 CYCLE REDUCI'IO4 PRXIRAM s i July 11 i Rev. 2, 1990 t EMERGENT ilDRE EVALUATION 110. . Mll0/FM/MR 110. DATE OLTIAGE NO. Attach To 1910 Before Sanding To The Control Room Description of Work RECOMMENDATION O ^pprov=1 Disapprovat Submitted by .Date ' Supervisor Approval Date YES NO, 4 O-T*'" r*9"tr** 'a 'c

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r= and is a significant threat to plant availability or capacity factor. Task is required to fulfill a conunitment. TRAC No. If any answer is yes, the task may be approved. Approved Disapproved AFM OF:;-FJ4-G/GF5 5upv Date 1 J

, ~. _ _. _ _ _ ?p% a., >3 m I a m m - a m ax,cassa men. W GHNE TWWE "B" SKIFT" ASFF. PIANT MMOGR MGNITNMU -f D. DERR30E 1 AIM 23 arurTPSGNT MADmMNG SUPE lRVIg3t.. MMSGlR BC. SUP. 0394. SUPERVISOR' BRIAN umma. T. s nwDiU R. BA w l S. reavuri 3 K DFLLTI'~ SUPERVISCNt P. wir m SWP 'RSK . MW:3E SPOG; BML Darm.i 'INIK DCIIEER TASK DGt TASK ENGR DER M I T. KHALID G. RAY h ' SHIPT ELECT star - ignus SHIFT I4C setu T SUPERVISOR SUPERVISOR SUPERVISOR SUPPORP SUPER R. 106r rus J. AIsu.ru B. RT(1RE, R. DORVG3 L h 9" TVAi

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4 9 e m 3 m DE4UW WE5 c OUDG MullK OM ORNEIRITCII i i ELECTRICAL WAINTENCE OUTAGE TEAM I 'B' SHIFT s h SHIFT ELECTRICAL c SUPERYlSOR = R ROBERTS SHIFT LEAD-DISCIPLINE SUPER. CSU SHIFT COORDINHTOR T. CILLIAW W.' WOULARD i i CWC CWC SUPERYlSOR SUPERYlSOR W. DEASON R. TAYLOR CSU CSU FACllliATOR FACILITATOR CIFRE0 WAYEAUX CSU - F DAE WAN:- CWC CWC CWC 0,' SHANNON _ FOREWAN FOREWAN FOREMAN WALBROUCH E J. AWATO J. TOOKER CSU CREU-GWC CWC CONTRAC ) TOTAL 12-CRAFT CRAFT TECHC ~ t TOTAL 14 TOTAL 14 -TOTAL e

F 3 N DE W UB Wit 5 i OTHER DWIUym mets Bar code tool control progran New shift schedules to inprove continuity PM progran optimization by System Engineering Preparation of contingency. job plans 5 0 tracking program one step check-in for contract enployees i l 1 l l-1 i

r.e ? x. J RF-3 Man-Ren Projects (Nove@er 1989) Painting 60.0 LIRT/ Repair 38.7 . ISI-Rx Vessel 32.6 Shielding 30,8 ISI-Wolds 29.9 Insulation Replacement 25.0 Control Pal Drive 19.9 l l Live Load Packing ~ 18,8 q ISI Snubbers 15.2 i - Flow Control Valves 13.0 ) DW Unit Coolers 4.0 1 i 1

BWRs LISTED IN ASCENDING ORDER OF TIIREE-YEAR AVERAGE COLLECTIVE DOSE PER REACTOR = Collective Dose Per Reactor Collective Dose Per Reactor (person-rem or person-cSv) Three-Year (person-rem or person-cSv) Three-Year Site Name 1987 1988 1989 Average Site Name 1987 1988 1989 Aveiagr Limerick-1 175 53 '302 177 hiillstone-1 684 144-462 430 Big Rock Poir.: 222 170 177 190 Perry 105 767* Vermont Yankee 303 124 288 238 I latch-1, -2 408 701 278 462 Cooper: 103 251 382 245 Duane Arnold 667 614 194 492 Fermi-2 255 Dresden-2, -3 623 705 565* 631 Clinton ' 130 418 Fitzpatrick ~940 786 377 701 117 287 465 290 Pilgrim 1579 392 207 726 Ilope Creek 311 258 352 307 Brunswick-1 -2 710 874 893* 825 Susquehanna-1, -2 Browns Ferry-1, -2, -3. 394 385 219 332 LaSalle County-l. -2 697 1236 693* 875 River Bend 378 107 558 348 Peach Bottom-2. -3 1098 1165 392-885 Grand Gulf 420 147 498 355 Oyster Creek 522 .1504 910* 979 Nine hfile' Point-1. -2 141 854 282 390 Wonticello 568 110 507 395 WNP-2 406 353 492-417 Annual BWR Averages: 527 529 439 Ouad Cities-1, 388 414 486 429 Total Reactors included: 32 34 36 ' Indicates high dose-per-reactor sites for 1989. Source: NRC. 4 w a

i BWR RECIRC PIPE DOSE RATES f g. j ( ,a*, 4 a'e 300-n u Z d N' e' E Non-Zinc Plante v ,o 3 ,/ River Bend l o 1 E / 200- ,/ o e o O o a j i e / i. m-o g / ,,,________________u_______._____________. a / n 100-l

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i in i ~ e L 1 RADIATION SOURCE TERM REDUCTION INTRODUCTION i TASK FORCE SHORT TERM RECOMMENDATIONS -1. Maximize the'une of short.and long cycleccleanup of condensate and feedwater= prior to start up for more effective metal removal.

2. Fully Incorporate cobalt removal concept into maintenance procedures-and sensitize maintenance' personnel to cleanliness methods when working on components containing cobalt.

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3. Evaluate Grand Gulf slow shut down method.

4.'. Sensitize Design Engineers to the incorporation of components-with reduced cobalt. 5._ContinueIto' implement effective methods of shielding and flushing.

6. Reschedule modification request 89-0240 designed to remove RNCU

' dead-legs from RF-4 to RF-3. t-ADDITIONAL RF-3 SOURCE TERM REDUCTION-ACTIVITIES i i V l l ~ l l lI f o

.. v. .i. ' : Fig. Changes of rediation exposure during schedu ec outage of TEPCO pants Old plant New plant O 1F-1 +. 2F-1 Q 1F-2 2F-2 2000 1F 2F3-1 F-4 2F-4 ) 1er 1F-5 A K-1 A1F-6 k ? 1500 e Ee (- .g-L 8 g 1000 (. g / 8 a I CU D, I to C 1 lj 500 J e-1br j f O O I I I i i '81 '82 '83 '84 '85 '86 '87 '88 - L Fiscal Year

- T.- c. L Fig-25 Fe crud deposition N za Ni, Co ion Surface of fuel rod acts F e crud -.as a crud filter T / 8 j Ni and Co ions without Fe crud deposit: C 'Co 2 directly on the surface of fuel rod in = aCo .g chemical forms of NiO and coo..Ni and - U% Co are easily release from the deposit, ? o N4[F e crud ,i Deposited Fe crud on the surface of fuell Ni. Co ion i c rod acts as a filter of Ni and Cc ions ' 4 \\ f. 3 s f-f [ Ni and Co ions with Fe crud deposit as - j 1 j t a eturmcal forms of NiFe20,,and CoFe,0,' 4C They have sufficiently lower solubil' ty-l i as compared with Nio and coo. i i Old plant 2F-1 2F-2, 2F-3 g Low Fe crud Suitable Fe crud l High Fe crud concentration concentration concentration GA L g pyh _ rp oS f, ;,o pp g (, gl T Ll a 8 e / i y ~ .E 1 m r o' A c U ( 4 j s m' .o Fe y 1-M .E- -o - d=F=i ed Niand Co nect release of deposited crud deposited Niand Coion t from thethickdeposition release again because of with Fecrud and become layer high solubility insoluble ] (insoluble radiation (soluble radiation sourm (soluble deposition on source to be deposited to be adsorbed on the the surface of fuel rod) on the bottom) pipe surface) m. 1 ( f \\ Dissolution rates of ferrites, such as nickel ferrite and cobalt ferrite are less than those of cobalt oxides and + nickel oxides by one order of magnitude. Legend 08 - ' Temp 280 E NiO -(A) A~ C o O (6) - pH 7 D g $ 0.6 k E -a 4 A 7 0.4 A i g. 6 ~ 0.2 g _ 9) - N i F e:0 ( / 9- -- Q - Q h~ CoFe:0. t g 0 1 2 3-4 '5 Time (h) Fig.-24 Dissolution Rates of Metal Oxides in High Temperatsre Water (Hitachi data)- L .= {- - -1 1 i i PLR (material: SUS 316L) CUW (material : carbon steel). j O "Mn .O "Mn O "Co -O "Co "Co O "Co 600 600 2 O= =. s s 1 e x E E 2 3 ! 400 E 400 = = m 5o ,o m

==, a 1 1 1 $ 200 $200 C-u 3 E- ~0 0 2 F-1 2 F-2 2 F-2 2 F-1 2 F-2.2 F-2 &~ 2 2 ? 2 2 2 8 8 8 8 8 8 i E 1 1 1 1 1~ G E i i Fig.-27 Comparison of dose rate between 2F-1 and 2F 2 Shut down dose rate of PLR and CUW piping at 2F 2 becomes 1/4 of the orw at 2F 1 l l

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F 1&BBR.10 t-R88 MRTALS-TRANSPORT: Fe/Mi Ratio Cycle 1 and Cvele (2) BWR-STRAM HP LP. CONDENSER GENERATOR TURBINE TURBINE RCS_ 8.5' (38) CDI 139 (97) FWS 5.7 (10.1) HP LP CONDENSATE HEATRRS HEATERS gj.g. DIMINS. ff_]LQ 10.9 (19.6) I --a

fl$naR TA i BB3 NRTAL8 TRANSPORit Total Cycle 1 and Crela (2) BNR STRAM RP IP CONDENSER GENBRATOR TURBINE '1URBINE RCS 21.2 ppb (106) 911. " 20 ppb gg (25.2) 1.63 ppb ' (1.57) HP LP CONDENSATE HEATERS REATER8 GJLI. osurN8. 1.3 ppb (2.6) i

11BRER_1 BBS MBTALs 7tApaPORft Total Cycle 1 and Crele (1) RWC5 1.20 " (6.0) ga/hr** BWR NP LP CONDENSER STRAM -TURBINE TUR31Ng GENERATOR B.GE. c_n 81 ga/hr (102) FW5 " 9.2 ge/hr (8.8) HP LP CONDENSATR HBATER8 ERATER8 QE[ DEMINS. ' 2.9 ge/hr8 6.3 ge/hr l(-1.7) (10,5) Calculated FFW-CDR sa Assuses 100% removal by RWC8 1 1 w

l FleURE 8 s RBS METALR TRABAP0Bff CORALT RWCS m I O.027 ge/hr (S)** 0.024 ge/hr (IS) CST 0.03-0.06 gm/hr BWR HP LP CONDENSER STRAM TURBINE TURBINE CENERATOR eel LW1 0.142 gm/hr 4 0.045 ge/hr (S)** 0.178 ss/hr (' " 0.186 ge/hr (IS) HP LP CONDENSATE HEATERS HEATERS ELL DEMINS. 0.065 ge/hr (S)** 0.195 ge/hr (IS) Calculated. FFW-CDE.

• • October 1989 Data
    • Based on 50 gym Makeup and 5/10/90 data (S): Soluble (IS)s Insoluble l

1

f 4 River Bend Station Source Term Reduction Long Term Action Items 9 k I f

1 Source Term Reduction Task Force ) i I o Initial recommendation for formation and kick off meeting held in August 19S0$7 o Membership of Task Force Engineering Maintenance Chemistry operations Radiation Protection Cost Systems Projects o Final report issued February 1990 by Chairman Phil Graham o Determined Co-60 is primary contributor o Final report identified three general goals Prevent introduction of cobalt into primary system Improve RBS cobalt removal efficiency Evaluate removal of cobalt by chemical decontamination and/or displacement (ZN) o Final report identified 13 separate recommendations Provided basis for our short term and long tern. goals 6 are complete or planned to be implemented 6 are ongoing activities or under evaluatien 1 has not been implemented based on additional review. o Action plan developed to implement Source Term Reduction Recommendations

O O e Long Term Action Items 1. Evaluate addition of filters for the hotwell, liquid radwaste, and the CST Preliminary study performed Contribution of CST and liquid radwaste to coolant metals is very small Additional filtration not needed for CST or liquid radwaste Evaluation required for hotwell to determine o Operational Requirements and constraints o Appropriate equipment o Equipment physical location o Cost / Benefit 2. Evaluate reactor water cleanup ring header modification / replacement Major contributor to drywell radiation Currently shielded during extended outages Will look at alternative routing and materials Potential RF-4 modification depending on results of evaluation Scope, schedule, and resource requirements to be determined (First Quarter 1997) 1 3. Remove " dead leg" hot spots through design changes Modification will include currently identified dead leg removal i Identification via Radiation Protection surveys L Recommended on case by case basis Evaluate changes based on ALARA cost benefits (manrem saved vs manrem spent for MOD) i

4. Evaluate the main steam isolation valve modification to reduce poppet r.nd guide rib wear. Current normal wear introduces large quantity of stellite into primary coolant loop Poppet and guide rib wear due to vibration 5. Review stellite applications and develop an ongoing program to reduce stellite usage. Investigate replacement material for stellite on MSIV guide ribs and seats (i.e. NOREM) o Plant Staff estimates 28 lbs of stellite or 14 lbs of cobalt is added per cycle for all 8 valves e o Final feedwater metal balance estimated.3 lbs of makes it to the vessel Replacement of control rods with stellite-free pins and rollers (24 control blades will be replaced RF-3) Identify components, particularly valves, where alternate material is appropriate Determine alternate material efficacy and availability Emphasis is on replacement parts and new equipment being purchased This will be done thru revision of_ equipment procurement specifications in cooperation with EQ Dept i 6. Continue to follow and evaluate industry experience with zine injection and chemical decontamination Radiation Protection maintains and updates information file with EEI/EPRI/ Chemistry workshop other departments monitor applicable activities at other facilities and evaluate potential for application at RBS

i 4 0 j m i 7. Evaluate cost / benefit of installing an online ion [ chromatograph to track / trend corrosion product transport Chemistry has determined this item is not cost effective o Current information is adequate for our purposes ? o High maintenance cost i o High operation cost i f i t 6 t i .l J

"J o l ~ f i Future Actions .t r o Continue with Task Force approach i i o Gather-required information/ data during RF-3 5 Radiological Engineering Walkdowns o Review and analyze results-e o Formulate specific action plan and schedule for RF-4 and beycnd during the first Quarter 1991 o Brief NRC on our action plan and schedules Visit Arlington during the first quarter of 1991 k f t i { r I l i h 4 6

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MEMoRAMDDM To J. C. Deddens September 8, 1989 FROM: P. D. Graham

SUBJECT:

Evaluation Results and Recommendations of the Clearance Program Improvement Task Force { The number of clearance related problems during RF-2, and subsequent NRC violation, focused management attention on the Clearance Program. A task force was formed to evaluate the i program and recommend improvements. This memorandum provides the recommendations of the task force and the supporting evaluation results. j Recommendations 1. Revise ADM-0027, Protective Tagging, to clearly and i simply address the following: I I a. Follow the INPO Good Practice, OP-203, format which { logically presents clearance requirements and required actions, t b. Consistency of Clearance Program " terms and definitions". - c. Clarify responsibilities. j d. Improve training requirements. e. Delete Attachment 7 and move necessary steps into i the body of the procedure, f. Simplify the Clearance Form (see INPO Good i Practice). NOTE: This will require Corporate Safety involvement and would result in changing the corporate form. g. Allow supplemental clearance release on a partial basis by signing a partial release form, h. Plant management should evaluate a requirement to allow only GSU employees to hold clearances. 2. Strengthen the training associated with Clearance Program requirements and assure contractor personnel have the knowledge and skill to implement the program as it applies to their activities..on-the-job training should be included. For example, a knowledgeable person could be assigned to each contractor during the first week of an outaga to help the contractor transition to the GSU program, 1.9 " shorten the learning curve".

g'N g. I Protective Tagging y River Bend Station Administrative Procedure ADM-0027, Protective Tagging - Total "from the ground up" revision - Developed by Clearance Program Improvement Task Force Operations Maintenance Computer Engineering Compliance Quality Executive Department Oversight Completed industry-survey through utility and vendor visits Developed for computer implementation 1 ~ Compatible with company safety tagging September 22, 1989 - commenced March-20, 1990 - ADM-0027, revision approved July 15, 1990 - Revision issued following qualification of plant-personnel . i I e __ _ )

o *. t -,= Y Procedure upgrede - ADM-0027 identified improvement issues: clarity and simplicity l- - Follows INPO Good Practice OP-203 - Maintains consistency of clearance program terms and definitions i .i - Clarifies responsibilities - Upgrades training and qualification requirements j i - Eliminates reliance on multiple procedures I s - Simplified clearance forms embody human factors i - Supplemental clearances replaced by multiple holders r Work packages include clearance receipts i - Enhanced program suitable for complex jobs and contractor use 1 n.. i t ? } I t 'I i i

l oj d. o p e t f: Training $sunary - Strengthened program encompasses demonstrated knowledge of the procedure, _ as well as skill in implementation - Formal training covers two days, and includes: Procedure

Industry Operating Experience Plant-$pecial Reference Documents Hardware Fundamentals

- Final qual card sign-off by Operations - Management involvement >in course development - Management feedback regarding presentation - All operators and Operations supervision qualified - Approximately 60 Maintenance supervisors, planners, technicians trained - Approximately-100 contractors trained

,'s a CLEADAtICE ~ - n., 3 Omt/ System /Ectipmet Ej CrearanceissuedTor. Date/Tema GJ Clearance Raiassad By-Dap3 rnmt 1 Ckarance Trar'sferred To: (Data /TPne) Transfarred Clea ance No. Frern l'urtose of Clearance WM MWR No. ~~ Sws.-.cs y Oearance inmal Str;W...;,yClearance hit a8 Date/Tirne Da C rna MWR No. Checked And Accepted Br VWR No. Raiaasad Or 1 1 i a ___f terder Of Protectrve Grcunds To Be hstsNed _ U Sea Attached Sheet For AddrtW SgG-m.h, Chara w.vs p Re4rence Mae Usad Fj Checked And AcceptedOr DaWTane Hj 1 S*gned DaWTW iagg ng Authorized by: Date/Twne 2-I Tag Ramoval Authonzad By-daw"rna 2 1 3 "sg Placement Completart br Ta00ed Tag namovat cow er Date/ Time Decornne Data /TW Supar mor 8 Wadramt4 t _... _ 1___..~___ F __ 2 w Double Venfy Confmed Entry Aubao *i 3 3__ Yes G No O ChackIrst Requwed? (Nuclear Plants Only) Yes O No O j C Pe=# Dj IJ [J~ C Tn e Tag w Tag 87 hm Fw oe ee 5,s ne No Devee Or Component Taggad omwr-e, Posmonmg Acton

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I 1 0 See Attached Continuation Sheet For Additional Tags

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