ML20195D867
| ML20195D867 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 11/03/1998 |
| From: | Hopkins J NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-MA3888, NUDOCS 9811180181 | |
| Download: ML20195D867 (20) | |
Text
{{#Wiki_filter:' November 3, 1998 LICENSEE: Illinois Power Company FACILITY: Clinton Power Station
SUBJECT:
SUMMARY
OF OCTOBER 27,1998. FEEDWATER LEAKAGE CONTROL SYSTEM MEETING (TAC NO. MA3888) On October 27,1998, NRC management and staff met in Rockville, Maryland, with representatives of lilinois Power Company (the licensee). The purpose of the meeting was to discuss a proposed feedwater leakage control system as described in the license amendment submittal dated October 23,1998. A list of the meeting participants is included as Attachment 1, and a copy of the meeting handout is provided as Attachment 2. The licensee discussed the feedwater penetration leakage history, an overview of the proposed leakage control system modification, and assumptions used in calculating radiation doses. The licensee is taking credit for suppression pool iodine scrubbing and used the ICRP 30 dose conversion factors for calculating the thyroid dose from airbome lodine. Licensee assumptions for operating the system post-accident include approximately 20 minutes to initiate the system and an additional 40 minutes to fill the system with water. Therefore, for the first hour post-accident it was assumed that there would be an air and water mixture being released through the leakage control system pathway. The licensee assumes that the first hour air flow will not be inhibited by any water sealant effect. The licensee has performed numerous tests to obtain a realistic conservative number for air leakage during the first hour. The NRC staff asked for the test information that supports the licensee's assumed air leakage during the j first hour post-accident. The licensee agreed to submit the supporting test information. Original signed by: Jon B. Hopkins, Senior Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-461 Attachments: 1. List of Meeting Participants
- 2. Meeting Handout cc w/atts: See next page DOCUMENT NAME: G:\\CLINTON\\1027.MTS OFFICE PD3-2:PM E
PD3-2:LA E PD3-2:D El NAME JHopkins /6 EBarnhill W SRichards eA \\ DATE h /A/98 '// /0@0f98 ~
- 1) /j/98 @M l OFFICIAL RECORD COPY C
\\ 9811100181 981103 PDR ADOCK 05000461 (LO2ChL
_m. _ _ _ _ _ _ _. _________.___._m_ yuy p 1 UNITED STATES s ] NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30seH001 DT November 3, 1998 LICENSEE: lilinois Power Company FACILITY: Clinton Power Station
SUBJECT:
SUMMARY
OF OCTOBER 27,1998 FEEDWATER LEAKAGE CONTROL l SYSTEM MEETING (TAC NO MA3888) On October 27,1998, NRC management and staff met in Rockville, Maryland, with represents,tives of Illinois Power Company (the licensee). The purpose of the meeting was to discuss a proposed feedwater leakage control system as described in the license amendment submittat dated October 23,1998. A list of the meeting participants is included as Attachment 1, and a copy of the meeting handout is provided as Attachment 2. The licensee discussed the feedwater penetration leakage history, an overview of the proposed leakage control system modification, and assumptions used in calculating radiation doses. The licensee is taking credit for suppression pool iodine scrubbing and used the ICRP 30 dose conversion factors for calNiating the thyroid dose from airborne iodine. Licensee assumptions for operating the system post-accident Ireclude approximately 20 minutes to initiate the system and an additional 40 minutes to fill the system with water. Therefore, for the first hour post accident it was assumed that there would be an air and water mixture being released through the leakage control system pathway. The licensee assumes that the first hour air f?ow will not be inhibited by any water sealant effect. The licensee has performed numerous tests to obtain a realistic conservstive number for air leakage during the first hour. The NRC staff asked for the test information that supports the licensee's assumed air leakage during the first hour post-accident. The licensee agreed to submit the supporting test information. I 6 Jon B. Hopkins, Senior roject Manager L Project Directorate 111-3 l Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-461 Attachments: 1. List of Meeting Participants
- 2. Meeting Handout cc w/stts: See next page 1
L
~ DISTRIBUTION FOR
SUMMARY
OF OCTOBER 27,1998, MEETING WITH ILLINOIS POWER COMPANY Hard Conv w/atts Docket File PD lll 3 Reading PUBLIC GGrant, Rlli l JHopkins 1 Hard Conv w/Att i OGC ACRS 1 E-mail w/Att 1 -SCollins (SJC1) FMiraglia (FJM) THiltz BBoger EAdensam (EGA1) SRichards Dross (SLM3)
. - ~. - -. - l, ~ l; Joseph V. Sipok Clinton Power Station, Unit 1 l' lilinois Power Company - cc: Walter G. MacFarland IV lilinois Department of Nuclear Safety Senior Vice President Office of Nuclear Facility Safety Clinton Power Station ATTN: Mr. Frank Nizidlek P.O. Box 678 1035 Outer Park Drive Clinton,IL 61727 Springfield,IL 62704 Wayne Romberg Leah Manning Stetzner Manager Nuclear Station VP, General Counsel & Corp. Secretary l Engineering Department 500 South 27th Street Clinton Power Station Decatur,IL 62525 l L . P.O. Box 678 Clinton,IL 61727 l Resident inspector U.S. Nuclear Regulatory Commission l RR#3, Box 229 A l .Clinton,IL 61727 l .R. T. Hill l l Licensing Services Manager j General Electric Company 175 Curtner Avenue, M/C 481 San Jose, CA 95125 Regional Administrator, Region lll U.S. Nuclear Regulatory Commission 801 Warrenville Road ' Lisle, IL 60532-4351 Chairman of DeWitt County c/o County Clerk's Office DeWitt County Courthouse Clinton,IL 61727 l' J. W. Blattner l_ Project Manager l Sargent & Lundy Engineers l 55 East Monroe Street (' Chicago,IL 60603 i I - - - - - - - +, .----e ce
MEETING ATTENDEES NRC AND ILLINOIS POWER COMPANY FEEDWATER LEAKAGE CONTROL SYSTEM MEETING OCTOBER 27,1998 1 l i g l J. Hopkins J. ' Pulsipher E. Throm M. Hart i lilinois Power Comoany l J. Sipek R. Phares E. Tiedemann T. Elwood l' D. Korneman J. Kaczmarek l Saraent & Lundv l W. Johnson (consultant to IP) 4 w
i ". 4 i 1 r-j } FeedwaterLeakage Control System i at Clinton Power Station October 27,1998 s 4 i 1 l 4 I IP Reoresentatives: R. F. Phares Manager-Nuclear Safety and Pertbrmance improvement }, J. V. Sipek Director-Ucensing f T. B. Elwood Supervisor-Ucensing Operations D. E. Korneman Pro}ect Manager-Engineen*ng [, E. E. Tiedemann SeniorUcensing Engineer J. F. Kaczmarek Ucensing Engineer W. J. Johnson Sargent & Lundy IF.LFNSIS PbWER
1 l.. i. Acienda l l Introduction J. V. Sipek t i 2 Feedwater Penetration Leakage J. F. Kaczmask i 4 Performance History FWLCS Overview D. E. Komeman T. B. Elwood I ) FWLCS Dose Assessment W.J. Johnson i i ' I l Project Schedule / Projected D. E. Komeman Completed Date Summary R. F. Phams f I ILLIM9ts PtNi.1liR .4
.l e. Feedwater Penetration Leakage Performance History Original Design and Configuration Modifications Made During Current Outage i ( l I i i l I i l i ILLINSIS PGAVER
F 8 TYPICAL FEEDWATER SYSTEM 3. Feedwater Lines. ANNULUS [ DRYWELL CONTAINMENT SillELD WALL INSIDE DUTSIDE INSIDE DUTSIDE INSIDE DUTSIDE [ s. ~ 2 b TO REACTOR 7 h h FEE 0w TER PRESSURE VESSEL -X-C><l- --L '. = = [ 3 Te by NTV
- .a
, netSSILE PROTECTED REACTOR TYPE: BWR g+ / ACTUATION / VALVE POSITION 9 4 g [ 4,:04 REMAR9(S i ss cwcx sacurtow optw cLosto T sg to 3-s no e att mort ss-e opta ctosto To",$ cLosto to 3-s No e 74%E Ytf7 sacurtow 2 SS asamunt optm cLosto Eo",08 asis to se no 7,${ 3 ss cart W (
gM '~ e* b b e h g O g ~ pw q ~~ W.
1 i FWLCS Overview Water Seal Function Connections to Existing Systems l F Leakage Flow for LOCA Proposed Technical Specification Changes 4 J I I !l 4 4 ILL!R@ts FOVIER
4 t 7 i ~ FEEDWATER CONTAINMENT - PENETRATION PIPING $HUTDOWN TO RE/CTOR COOLING FLOW FROM RHR L f I 3 i ) i ) -'=' r DIV 1 DIV 2 M.;., y FWLCS FWLCS I i "I" .)j -' CONTAINMENT
- ~[:'
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/1 1821F032 1 .. b'-. i ( m tr y i nn s & mde ~ l.. =. E l ' 1821F065 FEEDWATER ]' N 1 i i 8 i 5 N i 1 M F M M ME us swwe su 1 h
q. ~ j. \\/ [;
- FWLCS PIPING SCHEMATIC d^
Cig >C 51 l E2F011A E2F010A ' g. 22F032A E2F065A E12F498A 2 l E12F500A l TC[ > " 1E12F526A TC[ >,J ' 4 /-{ f 1E12F524A IE12F523A 1E12F525A 2" TC[ > ' Il2f499^ IE12F504A 1E12F503A 2" {1E12F501A[E7 E12F027A 2-1 h E12F042A VgT ~ 1E12F520 1E12F508 /V RHR PUMP A [ 1E12F522A A Ib k 1E12r52 B 2i/,- i h E12F497 IE12F521A ,,{ ENT 1E12N664 'l TC[ > ' ?, E12F496 1E12F505 M g 1E12F521B h 2" ll( 1E12F l Et2r042B' Eur0278 IE12F503B 2" RHR PUMP B lr 3 w2 w2 ( E12F4958 1E12F499B E 2F5028 l _\\{ IE12F5268 .{ IE12F524B 2" 2" TC,. u,, lI TC[ r 4 1E12F5258 Euf5M 1E12F5238 E12F438B 2" 162 Fore E27010B B2T0328 [ r x y y i R$ B
- I TC TEST CONNECTION (S/D i
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- 3..
l.- l. _EA(AGE
- _0W 20R
_0CA i ( !~ I l L1 =-ENVIRONS o GAS CONTROL l-BOUNDRY ANNULUS f l l1 OTS I RYWEL A L5 2 _s e e cm. MSIV ~ LCS l' i l' l l RPV t l l CONTAINMENT BREAK L4 V n l - SUPPRESSION O O POOL 0 ,0 t i e i u-
'~ _EA(AGE
- _0W 20R
_0CA (W::Ti W_CS) = ENVIRONS I o GAS CONTROL BOUNDRY ANNULUS SOTS = RYWEL A L5 2 s amamammaum c.- MSIV LCS FEE 0 WATER L6 RPV CONTAINMENT PENETRATIONS CONTAINMENT BREAK L4 FWLCS b SUPPRESSION C 0 POOL A-J' f k .I l-
FWLCS Dose Assessment Description of Dose Model Effects of Using Suppression Pool Scrubbing and ICRP 30 1 1 i { l l .I t RLLtK@ls POVER I ~~~~
t
- 2 Summary of Radiological Effects (Rem) i t
30-Day Current CPS Effect ofusing FWLCS dose Proposed new 10CFR50 i-MCR Licensing Basis
- POSTDBA, calculation CPS Licensing Appendix A Dose (as ICRP 30, *"
results *" Basis Dose "* GDC 19 Limit reflected in the and suppression. (DBA LOCA) (SRP 6.4.11.6) l USAR) pool scrubbing ]. Thyroid 4.3 (27)* 2.874 8.624 8.6 30 y-Whole 2.0 2.524 3.51 *
- 3.5 5
j Body p-Skin 14.3 13.69 17.10 17.1 30 2-Hour Current CPS Effect ofusing FWLCS dose Proposed new 10CFR100.11 EAB Licensing Basis
- POSTDBA, calculation CPS Licensing Limit Dose (as ICRP 30, *"
results "* Basis Dose "* reflected in the and suppression (DBA-LOCA) USAR) pool scrubbing Thyroid 163 17.31 198.1 198 300 y-Whole 4.4 3.728 9.786 9.3 25 Body 30-Day Current CPS Effect ofusing FWLCS dose Proposed new 10CFR100.11 LPZ Licensing Basis
- POSTDBA, calculation CPS Licensing Limit Dose (as ICRP 30, '"
results "* Basis Dose *" reflected in the and suppression (DBA-LOCA) USAR) pool scrubbing Thyroid 156 17.57 f 76.04 76 300 y-Whole 1.7 1.549 2.981 3.0 25 Body
- The 27 rem value was previously allowed when accounting for 650 cfm of filtered duct leakage. The dose model used for calculating the FWLCS dose included and accounted for filtered duct leakage.
" This value iracludes aproximately 0.459 rem from external shine sources. "* TCRP 30 dose conversion factors were used for thyroid doses. Reg. Guide 1.109 dose conversion factors were used for y-whole body and p-skin doses. I i ILLi m tS POWER I ' ~T: ~ ' ' " ~
~ Project Schedule / Projected Completion Date Division 1 Tie-Ins to RHR and FW are Complete I Flow Testing is Currently Scheduled for Late November /Early December Project Estimated to be Completed by the end of December t II.LitMIS PC/WER
\\ ?. November 3, 1998 LICENSEE: lilinois Power Company FACILITY; Clinton Power Station
SUBJECT:
SUMMARY
OF OCTOBER 27,1998, FEEDWATER LEAKAGE CONTROL . SYSTEM MEETING (TAC NO. MA3888) On October 27,1998, NRC management and staff met in Rockville, Maryland, with representatives of I!!inois Power Company (the licensee). The purpose of the meeting was to discuss a proposed feedwater leakage control system as described in the license amendment submittal dated October 23,1998. A list of the meeting participants is included as Attachment 1, and a copy of the meeting handout is provided as Attachment 2. The licerisee discussed the feedwater penetration leakage history, an overview of the proposed leake3e control system modification, and assumptions used in calculating radiation doses. The licensee is taking credit for suppression pool lodine scrubbing and used the ICRP 30 dose conversion factors for calculating the thyroid dose from airbome lodine. Licensee assumptions for operating the system post-accident include approximately 20 minutes to initiate the system and an additional 40 minutes to fill the system with water. Therefore, for the first hour post-accident it was assumed that there would be an air and water mixture being released through the leakage control system pathway. The licensee assumes that the first hour air flow will not be inhibited by any water sealant effect. The licensee has performed numerous tests to obtain a realistic conservative number for air leakage during the first hour. The NRC staff asked for the test Information that supports the licensee's assumed air leakage during the first hour post-accident. The licensee agreed to submit the supporting test information, Original signed by: Jon B. Hopkins, Senior Project Manager Project Directorate 111-3 Division of Reactor Projects lil/lV Office of Nuclear Reactor Regulation Docket No. 50-461 Attachments: 1. List of Meeting Participants
- 2. Meeting Handout cc w/atts: See next page DOCUMENT NAME: G:\\CLINTON\\1027.MTS OFFICE PD3-2:PM E. PD3-2:LA E
PD3-2:D E NAME JHopkins /6 EBamhill 9h SRichards e/ DATE ll /A/98 4/ /0#ju98 ~
- 1) /_^j/98 (72W OFFICIAL RECORD COPY
Distribution: Hard conv PUBLIC Docket File, PDLR RF M. El-Zeftawy, ACRS T2E2 E-mail: F. Miraglia John Ma J. Roe D. Matthews C. Grimes T. Essig G. Lainas J. Strosnider G. Bagchi H. Brammer T. Hiltz G. Holahan S. Newberry C, Gratton L. Spessard R. Correia R. Latta 4 J. Peralta J. Moore R. Weisman M. Zobler i E. Hackett A. Murphy T. Martin D. Martin W. McDowell S. Droggitis PDLR Staff H. Berkow D. LaBarge L. Plisco C.Oge R. Trojanowski M. Scott C. Julian R. Architzel.' J. Wilson. R.Wessman E. Sullivan R.- Gill, Duke D. Walters, NEl -}}