ML20057F281

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Summary of 930929 Meeting W/Util Re Installation of Water Level Monitoring Instrumentation at Plant.List of Attendees & Presentation Slides Encl
ML20057F281
Person / Time
Site: Monticello 
Issue date: 10/12/1993
From: Gamberoni M
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
IEB-93-003, IEB-93-3, NUDOCS 9310150069
Download: ML20057F281 (41)
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Text

{{#Wiki_filter:' October 12, 1993 Docket No. 50-263 LICENSEE: Northern States Power Company FACILITY: Monticello Nuclear Power Plant

SUBJECT:

INSTALLATION OF WATER LEVEL MONITORING INSTRUMENTATION AT MONTICELLO NUCLEAR POWER PLANT A meeting was held at NRC Headquarters on September 29, 1993, to discuss the installation of water level monitoring instrumentation at the Monticello Nuclear Power Plant. A complete list of attendees is attached as Enclosure 1. A copy of the presentation slides is attached as Enclosure 2. 1 Northern States Power's presentation included a history of Monticello's reactor water level instrumentation changes, a discussion of the current water' level instrumentation and a discussion of the planned hardware modifications. 1 The current status of the planned hardware modifications shows the non-outage portion of the installation as near complete; and the thermal analysis, safety evaluation and preoperational test procedures all in progress. The current schedule indicates all work to support outage installation and testing will be complete by December 31, 1993. NRC Bulletin 93-03, " Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs" requested all licensees to implement modifications at the first cold shutdown after July 30, 1993. The staff is evaluating Monticello's proposed schedule and will provide a written response. In addition, the staff has requested information from any preliminary testing performed prior to installation. Original Signed By: Marsha Gamberoni, Project Manager Project Directorate III-l Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosures:

1. List of Attendees 2. Presentation Slides cc w/ enclosures: See next page MGamberonisf(a WDean g jh D:PDII LA:PDIII-4 M:PDIII-1 CJamerson u b 10/l /93 Y 10/1/93 10/cq /93 J Lg OFFICIAL FILE COPY FILENAME: G:\\WPDOCS\\MONTICEL\\ MON 929MT. SUM gl h6 e O$ g;;rK4 [fffY . g.- MM* 9310150069 931012 PDR ADOCK 05000263 G PDR

. DATED: October 12, 1993 DISTRIBUTION FOR

SUMMARY

OF SEPTEMBER 29. 1993. MEETING (W/ENCLS. 1 & 2); Docket File NRC & Local PDRs PD31 Reading File J. Roe J. Zwolinski B. Jorgensen, Rill M. Gamberoni DISTRIBUTION (w/o Encl. 2) T. Murley/F. Miraglia (12-G-18) J. Partlow (12-G-18) OGC E. Jordan (MNBB 3701) ACRS (10) B. McCabe, EDO (17-G-21) A. Cubbage R. Frahm K. Graney J. Clifford W. Dean C. Jamerson cc: Licensee & Service List 140032 SFo( ni

p arcg ll % ~' % a )e() E UNITED STATES S(i ) g'# ! NUCLEAR REGULATORY COMMISSION l v / WASHINGTON, D.C. 20555-0001 ....+ October 12, 1993 l Docket No. 50-263 LICENSEE: Northern States Power Company l FACILITY: Monticello Nuclear Power Plant l

SUBJECT:

INSTALLATION OF WATER LEVEL MONITORING INSTRUMENTATION AT MONTICELLO NUCLEAR POWER PLANT l A meeting was held at NRC Headquarters on September 29, 1993, to discuss the l installation of water level monitoring instrumentation at the Monticello Nuclear Power Plant. A complete list of attendees is attached as Enclosure 1. A copy of the presentation slides is attached as Enclosure 2. Northern States Power's presentation included a history of Monticello's reactor water level instrumentation changes, a discussion of the current water level instrumentation and a discussion of the planned hardware modifications. The current status of the planned hardware modifications shows the non-outage portion of the installation as near complete; and the thermal analysis, safety evaluation and preoperational test procedures all in progress. The current l schedule indicates all work to support outage installation and testing will be i complete by December 31, 1993. { NRC Bulletin 93-03, " Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs" requested all licensees to implement modifications at the first cold shutdown after July 30, 1993. The staff is evaluating Monticello's proposed schedule and will provide a written response. In addition, the staff has requested information from any preliminary testing performed prior to installation. I\\ tv.shc. c~lm~ l Marsha Gamberoni, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosures:

1. List of Attendees 2. Presentation Slides cc w/ enclosures: See next page k

Northern States Power Company Monticello Nuclear Power Plant cc: Mr. Roger O. Anderson, Director Kris Sanda, Commissioner Licensing and Management Issues Department of Public Service Northern States Power Company 121 Seventh Place East 414 Nicollet Mall Suite 200 Minneapolis, Minnesota 55401 St. Paul, Minnesota 55101-2145 J. E. Silberg, Esquire Lisa R. Tiegel Shaw, Pittman, Potts and Trowbridge Assistant Attorney General 2300 N Street, N. W. Environmental Protection Division Washington DC 20037 Suite 200 520 Lafayette Road U.S. Nuclear Regulatory Commission St. Paul, Minnesota 55155 Resident Inspector Office 2807 W. County Road 75 Monticello, Minnesota 55362 Site General Manager Monticello Nuclear Generating Plant Northern States Power Company Monticello, Minnesota 55362 Robert Nelson, President Minnesota Environmental Control Citizens Association (MECCA) 1051 South McKnight Road St. Paul, Minnesota 55119 Commissioner Minnesota Pollution Control Agency 520 Lafayette Road St. Paul, Minnesota 55119 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Commissioner of Health Minnesota Department of Health 717 Delaware Street, S. E. l Minneapolis, Minnesota 55440 Darla Groshens, Auditor / Treasurer Wright County Government Center i 10 NW Second Street Buffalo, Minnesota 55313 h@ lW3 i 's

Meeting Attendance September 29, 1993 NAME AFFILIATION Marsha Gamberoni DRPW/NRR/NRC Amy Cubbage DSSA/NRR/NRC Ron Frahm DSSA/NRR/NRC l Kevin Graney SERCH Licensing /Bechtel Jim Clifford DRPW/NRR/NRC Bill Hill Northern States Power Ramsay Sawaya Northern States Power James Gausman Northern States Power Bob Samworth DRPW/NRR/NRC Roger 0. Anderson Northern States Power Bill Dean DRPW/NRR/NRC I )

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4 "[ AGENDA FOR 9/29/93 MEETING V" l l ^ ON MNGP REACTOR WATER LEVEL INSTRUMENTATION 2 l t

1. INTRODUCTIONS i

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2. HISTORY OF REACTOR WATER LEVEL 3

1~ INSTRUMENTATION ISSUES AT 4 l w.. MONTICELLO u. kk

  • PAST INSTRUMENTATION CHANGES

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3. DISCUSSION OF CURRENT WATER LEVEL C

INSTRUMENTATION 3 i y'

  • SAFEGUARDS & FUEL ZONE REFERENCE LEG DESIGN AND' CONFIGURATION N

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  • MONITORING OF SYSTEM PERFORMANCE 3

m i DURING RECENT SHUTDO'NN i W COMPENSA17./ MEASURES TAKEN IN W RESPONSE TO INDUSTRY /NRC CONCERNS } l t

4. DISCUSSION OF PLANNED HARDWARE w

MODIFICATIONS - OPTIONS CONSIDERED AND REASONS FOR b: I ~ SELECTING BACKFILL MODIFICATION u T

  • DESIGN DETAILS OF MODIFICATION SELECTED Q

< n, w T = OUTSTANDING TECHNICAL ISSUES 'b y ASSOCIATED WITH BACKFILL MODIFICATION [ l 7 -m . SCHEDULE yd y, 9

5.

SUMMARY

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1. PREVENTION OF REFERENCE LEG OVERHEATING OR REDUCTION OF THE VERTICAL DROP IN THE DRYWELL i
2. REPLACE MECHANICAL LEVEL INDICATION WITH ANALOG LEVEL TRANSMITTERS

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i I A DRYWELL j REACTOR DRYWELL PRESSURE WALL VESSEL% ~ACCOMuaTM C B S ~ t lD RL ROOM "E SHELL LE k * [ REFERENCE LEG ~.- VARtABLE LEG N N HEAT ) AjSfER \\ p . /g$'u / Ct4LY) \\ j WATER F = M \\ ap CELL -I/oh159 3

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1. SAFEGUARDS LEVEL COLUMN 1

PIPING MODIFIED TO MINIMlZE VERTICAL DROP INSIDE [ CONTAINMENT (COLD j POTS VS. YARWAYS)

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2. MECHANICAL LEVEL INSTRU-MENTATION WAS REPLACED j

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x PAST EXPERIENCE HAS REVEALED THE SENSITIVE NATURE OF THIS o x SYSTEM TO MODIFICATIONS. i ^

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(CONT'D) A THOROUGH ANALYSIS AND TESTING IS REQUIRED TO ASSURE 1 NO NEW SAFETY CONCERNS ARE t INTRODUCED. F r I .,b 'l c g pn p.:. ~ a l I I t ~ f;^ %3 'W [ I -3 v Q;. ~ A}.k y iO 's. y , w; 1/oh159 8 . J

f DESIGN & CONFIGURATION MARGIN AVAILABLE FOR RHR S/D COOLING ISOLATION IS LARGE FAILURE OF ONE REFERENCE LEG DOES NOT PREVENT S/D COOLING ISOLATION THE SAFEGUARDS REFERENCE LEG PIPING USED AT MNGP IS 1" FROM THE POT TO THE RACK AUTOMATIC VALVE INTERLOCKS MINIMlZE THE PROBABILITY OF DRAINDOWN EVENTS . ENHANCEMENTS TO THE PLANT COMPUTER SYSTEM HAVE BEEN IMPLEMENTED. I/oh159 '9

? REACTOR SAFEGUARDS INSTRUMENTS SKETCH OF INSTRUMENT LINES t i

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'~ ^ (- s s [ ) F r COMPENSATORY / MEASURES e i MONITORED FOR NOTCHING COMPLETED DURING SHUTDOWN

  • PERFORMED WALKDOWNS COMPLETED OF THE SAFEGUARDS REFERENCE LEG PIPING ENHANCED MANUAL COMPLETED BACKFLUSH OF THE REFERENCE LEGS BEFORE STARTUP v :. "

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+ COMPENSATORY MEASURES ~ (CONT'D) i -i

  • TRENDED WATER LEVEL ON GOING S

DAILY AVERAGES i

  • PERIODICALLY MONITORED ON GOING REFERENCE LEGS FOR LEAKAGE

'c

  • OPERATOR PROCEDURE COMPLETED ENHANCEMENTS T

Y ~ s .4 9 $fQd s l 7 ,e. m 9.g f $m.. pi r4 aegM i, '$h 1/oh159 20 i

P v COMPENSATORY MEASURES (CONT'D) ENHANCEMENTS TO THE COMPLETED PLANT COMPUTER SYSTEM OPERATOR GUIDELINES, COMPLETED = BASED ON A SAFETY EVALUATION AND A PRA CALCULATION ABNORMAL PROCEDURE COMPLETED AND A MANUAL BACKFILL-PROCEDURE WITH THE CORRESPONDING THERMAL STRESSES CALCULATION EXTENSIVE OPERATOR COMPLETED TRAINING ON NON-CONDENSIBLE ISSUE DURING RAPID AND SLOW DEPRESSURIZATION QQ + 1/oh159 21

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SUMMARY

l IN VIEW OF THE ABOVE, WE BELIEVE THAT THE EXISTING MONTICELLO REACTOR WATER LEVEL INSTRUMENTATION, IN CONJUNCTION WITH THE COMPENSATORY MEASURES IS ADEQUATE TO ENSURE THE CONTINUED I HEALTH AND SAFETY OF THE PUBLIC. HOWEVER, WE ARE PURSUING ENHANCEMENT ON AN EXPEDITED BASIS. l l 1 \\ f J = .a 22 l

s -w.- 3' 'Y 5, g, ;,hf, -)- y , l. ' h',' i f 9 m l ., Nd ' i HARDWARE MODIFICATIONS OPTIONS CONSIDERED AND REASONS FOR SELECTING a BACKFILL MODIFICATION DESCRIPTION OF MODIFICATION OUTSTANDING TECHNICAL ISSUES SCHEDULE f.:l4 ' l ?!. s I ^ f;U' _f.'f ' l n i g. f-f $"" (. t . :n L? v l [&$ fN

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"j 7 %.};Ei t Z ijy 'M ' ^ y _.g.5 ~ 4 f y MODIFICATION PROCESS 4 s N

  • ENSURING THE PROBLEM WAS FULLY DEFINED w

2f

  • GENERATING ALTERNATIVE l

SOLUTIONS -_ y). kN.b

  • EVALUATING ALTERNATIVE 0;

SOLUTIONS s SELECTING THE OPTIMUM l ~ SOLUTION ON THE BASIS OF PERFORMANCE, COST AND J e SCHEDULE d a w yz; ,~ i 'v,, j'- k I-' JQ" s. 3P; W en

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I T>'[] "\\ .. I... -. x (s 6'h ^ -i $2j ";;.k,?} O / jj ' R -4 7, G _ ;:p._ sq, -:p V 1't P 's f 6 ALTERNATIVE DESIGNS ^ 5:f ^ b i BACKFILL SYSTEM i f A _,3.

  • m CONDENSING CHAMBER VENT a

CORE RANGE MONITORING i -f ABB TYPE CONDENSING CHAMBER f s "OTHER CONDENSING CHAMBER S MODIFICATIONS" x x l i . t.:

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4 ( %h I s Y N 9 ' "- REASONS FOR BACKFILL 1 MODIFICATION T -f{%Q" BWROG GUIDANCE i I NRC IMPLIED ACCEPTANCE OF THIS APPROACH i -.j% +, i y SHORTEST LEAD TIME TO

J DEVELOP DESIGN 1

.i LEAST OUTAGE TIME REQUIRED r

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e v ).' / ^ ( h DESIGN FEATURES ~ r WATER SUPPLIED FROM CRD . SLOPED TUBING FILTERS FLOW METERS WITH ESSENTIAL POWER SUPPLY DUAL METERING VALVES CHECK VALVES l l l = INJECTION POINT IS INTO 1" PIPE AWAY FROM INSTRUMENT RACK l ~ LOCKING OF REFERENCE LEG ISOLATION VALVES IN THE OPEN POSITION m y i + : m ;. :: :yg my ngl Lug:Q, 1/oh161

t1 3/8' DC l !CRD_14-2l 3 " TUDE x 0.065! l l0F-12l leF-14l J g8F-15l /g et u i o, cc 3-3A T Ier-illeF-21i l IB i 'T -tAGDE: eF-si b lr-61 =y cizi rutt lA: A: dk: lyl-l-NBF-13l lBF-16l E T FE-4813A { Ml l BF-8 ll BF-9 llBF-10ll (C.5) l lBF-7l l1 MDF-11l o lO a l er-3 ll eF-4 l l t l i 3u i i -l Cao-15 I l n-4814A l lBF-24l l8F-26l J T-27! .L l ,.aL l RLM1-T-DC8 g i lor-17l l8F-19l i c i: % CC 2-3-2A gjg l --tA:, _g lA: tyl-l-Wor-23l ler-sil 0-1is) 1 9, e. l lBF-20llBF-21llBF-22ll 1 $$v lBF-18] kBF-23l 3/ TUBE x 0.065-5 B l 8 'q i iO I I i O I I l "-48[8 l ler-3sl ler-37l J dF-381 j leF_2el y leF-30l j d' N ,e q CC 2-3-28 l'--tA: g8 l l BF-36l lF-32l O -116 ) U (9,3) ler-3il[er-32ller-331: i l lej291 dBF-34l J,= M x OMN f l l 3/8* DC r' l l [eF-461 "-4813B leF-4al deF-49] l lBF-39] lBF-41] C122 FUEt Z l E g8 l F-Q F-47l lW-50l (,- 6) ' i lor-42llBr-43ller-44l: O I (C.3) l lBF-40l l1 MBF-451 ~~ i mL 1 t_________:_____________________;g i . RACK C-353 28 m 38, uonn cro

~ NEW CRD-142 PIPE j s BF-1 BF-2 = X %res@ To"Er SIDE j CRD-141 FF-u BF-3 BF 4 so m l BF 18 BF-17 I b i METERING VALVE % BF-20 BF-21 $4 BF-19 [ BF-22 6 NEW y I SV BF-10 BF-9 BF-8 BF-6 BF-5 $J L l l LJ SR f M M ofh ~ METERING yJ ] vAtvE _3 3,_,3 BF-26 [ II3 SR ? . P BF-28 2A BF-15 I BF-12 BF-14 M REACTOR ,Qg g T O VESSEL I 3 g y BF-16 D BF-11 BF-13 j g l RACKC55 l LJ LJ NSD ,PSD NSD %2^ W^ W" JX-25A T c55 [LTh tt38 tw2_A T 1x-w 1 c121 ci21 [LTD /TJE\\ Qg112B Q 73A Jxaon M JP T ./ A REACTOR VESSEL LEVEL BACKFILL STATION (TYP) gg 1/oh161

y t ' fE .. = - # ' $ ' bb I ^ >, i h. ) :. I ^ M'? ' y? s. ;- g'y:Ia , *. f ' jyi?; ' }s;:gg,p}igjfp!gyg[-.g 4p;;m g,' ; 5 4F- >m 9 e. E t 3 i i s OUTSTANDING TECHNICAL ISSUES 1 4 [ [ x ~ MAXIMUM ALLOWABLE FLOW RATE i TRANSIENTS FROM CRD ~ TRANSMITTED TO i REFERENCE LEGS 1

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L {' Om.. $5y _Qi O ~. s,_ _[> Fil }Qf, g[Nf$ gh ' 951.;,,, ij y,{g [li " 1 j J. R x 4 l t MAXIMUM ALLOWABLE FLOW RATE C 4 TWO REFERENCE LEGS i CONNECTED TO EACH RPV NOZZLE e SHORT CONDENSING ~ CHAMBER TO RPV STEAM LINES ~ 1 STATUS ~ i ACCEPTABLE MAXIMUM i FLOW RATE IS LIKELY 7 j r ANALYSIS IN PROGRESS

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,I ( Y.- '[ '(,, - ~ i[4 y . 4 J( i/ v, ? TRANSIENTS FROM CRD 4 TRANSMITTED TO REFERENCE LEGS .1 I

  • MONTICELLO OPERATING

'1 HISTORY SHOWS SENSITIVITY OF INSTRUMENTS MONTICELLO CRD PRESSURE TRANSIENTS C WERE OBSERVED 6 + STATUS PRESSURE TRANSIENTS WERE CONSIDERED IN DESIGN PHASE . PLAN TO TEST NEW SYSTEM m PRIOR TO COLD SHUTDOWN . WILL DESIGN AND INSTALL m i .J ADDITIONAL DAMPENING IF C REQUIRED sy z ^;( ~ J,' i l: r g B luj+'. K ;e yy* e; :. 1/oh161 32

1 p = - - n -- - - 2 ^ m T-Z ,7 z -- ^ -W-- 1 _" = ' L_ T .T. O 2 2 =" ~_ ~_ T- ' ~ L" ,_z .T . ;~ V'Y.w 3 ~ M _^ r r 7 EElli - 56'_ ~ .~ ~ ee ~ N$ E.-%", -y ^, W i - =::S3 5.- - f .'l I -=- MM 3-__ ~ '-~'L -4_R_ .M B E ~ 'w x = tis -.' .~ M__- M ~_ 1 w = y f "_-m g 3 n== Q .= ii _." .c. a = ,a. i _E_E.mKIlg-E ,d -'a 8 c- _7-_ B_ l - -r ^ = = p m = S m E h ."F m" z = ~~.^. ~ 4 }. .2 _T e r" d T T 1 8 1 -1 m h ^m.+*,~ [ -M1 m .L .w+- 4~%*,5 P. = __y_ .s .w N f ~y r _ N - ~2--dJ i_ m, i -h- -y ~ m--_m.. 1 t " ~ -.*=? M.. ". --=,'y . % a ng e i ~

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1; t ~.? k ?.f^^ / t~ + i i BASIS FOR SCHEDULE SUBMITTED IN RESPONSE TO NRCB 93-03 i = BACKFILL MODIFICATION FROM CRD

  • INSTALLATION IN PARALLEL WITH SAFETY EVALUATION i

. MONTICELLO SPECIFIC ISSUES H. EXPERIENCE WITH FAST TRACK i PROJECTS i l EXPERIENCE WITH REACTOR LEVEL ~. I INSTRUMENTATION MODIFICATIONS . HIGH CONFIDENCE LEVEL GIVEN THE UNCERTAINTIES ~ l y %f j:d ',, ' W [ l'], Q ; s; ; y 1/oh161

.sd s I f y f ) CURRENT STATUS r ~ NON-OUTAGE INSTALLATION - IN PROGESS THERMAL ANALYSIS -IN PROGRESS . SAFETY EVALUATION - FIRST DRAFT ". COMPLETE i

  • PREOPERATION TEST PROCEDURES

- BEING WRITTEN t l . EXPECT ALL WORK TO SUPPORT OUTAGE INSTALLATION AND TESTING WILL BE COMPLETE BY DECEMBER 31ST,1993 + y ycygpr - s e f =t

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SUMMARY

  • BACKFIL.L MODIFICATION IS BEING INSTALLED e

. RESOLUTION OF TECHNICAL ~ ISSUES IN PROGRESS . EXPECT TO INSTALL AND TEST AT NEXT COLD

x SHUTDOWN FOLLOWING DECEMBER 31.1993

'? a y.i. , ;; A : L ' ~ '*:3 Q' Qf)W ^ e 1/0h161 37

MONTICELLO NUCLEAR PLANT REACTOR VESSEL - -.. - -.. = ..---=-n~~- e s l l _ Wr I ') 1 s a 'i .F 0 3 ) (* h f! 'k 4,. ;V V d c l

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