ML20195E543

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Submits Status Summary Rept on Multi-Plant Action B-66, Natural Circulation Cooldown. Near-term OLs Should Not Be Added to Safety Issues Mgt Sys Listing for Subj Action
ML20195E543
Person / Time
Site: Davis Besse, Oconee, Three Mile Island, 05000000
Issue date: 06/10/1988
From: Capra R, Hodges M
Office of Nuclear Reactor Regulation
To: Varga S
Office of Nuclear Reactor Regulation
References
GL-88-21, TAC-M47146, TAC-M47158, TAC-M47159, TAC-M47161, TAC-M47164, TAC-M47165, TAC-M47166, TAC-M47171, TAC-M47172, TAC-M47173, TAC-M47176, TAC-M47180, TAC-M47181, TAC-M47182, TAC-M51994, NUDOCS 8806240076
Download: ML20195E543 (6)


Text

_ _ _ _ _ _ _ _ - _ _ _

. June 10, 1988 .

MEMORANDilM FOR: Steven A. Varga, Director DISTRIBUTION Division of Reactor Projects, I/II =CaptseLJ11 era -

Office of Nuclear Reactor Regulation NRCPDR Local PDR FROM: Robert A. Capra, Director ?DI-1 Rdg.

Project Directorate I-1 BBoger Division of Reactor Projects, I/II CVogan

( Marvin W. Hodges, ihuf SMcNeil MWHodges Reactor Systens Branch RJones Divisior, of Engineering and RCapra l System Technology SUB.1ECT: MPA B-66, NATURAL C16CULATION C00LDOWN STATUS

SUMMARY

REPORT

1. Safety Significance

In evaluating the effects of void formation occurring during natural circulation cooldown of PWRs, the Reactor Systems Branch staff has detemined that this void fomation will not significantly impair core decay heat removal when appropriate emergency operating procedural guidance is provided to mitigate any void effects. The appropriate proccJural guidance has been reviewed and approved on a generic basis by the NRC staff. Consequently, the staff has concluded that MPA B-66 is not a safety *,ignificant issue for any PWRs with the exception of Davis-Basse I wF.1 h has implemented a unique head design modification.

P. Current Plan.

Currently, safety evaluations have been completed and sent to all pre-TMI-2

01. PWRs with the exception of Davis-Besse 1. The Davis-Pesse review has slipped into 1989 due to the licensee's failure to provide the required information to permit completion of the NRC review. The only plant where implementation of B-66 is not complete 's Oconee 1 and 2 where inplementation completion is scheduled for 1990.

In addition, all of the regions are now perfoming TI ?.515/86 to verify that all PWRs have implemented programs for the control of natural circulation cooldown in sccordance with GL 81-21.

In sumary, B-66 is not scheduled to be fully complete until after 1990.

3. Proposed Plan The staff review of 8-66 is complete for all PWRs that were OLs prior to the TMI-2 accident with the exception of Davis-Besse 1. For all TMI-2 NTDLs, void formation was considered in BTP RSB 5-1, "Design Requirements un88= 8:8%r A'

44 hl

'p f P f

e of the Residual Heat Removal System" of the Standard Review Plan.

Consequently, the effects of void formation for each NTOL were analyzed in each plant's Safety Evaluation Report during the plant licensing process.

It is therefore recommended that this issue be closed out as an MPA for all PWRs with future Davis-Besse review conducted as a plant-specific licensing action and with the Oconee 1 and 2 implementation maintained as a plant-specific TAC with that sole purpose. The Davis-Besse and Oconee Project Managers shall be requested to take out TACs for these issues.

Furthermore, it is recommended that the NT0LS not be added to the SIMS listing for this MPA, rather a statement providing the details of this issue's incorporation into the BTP RSB 5-1 review should be included in the SIMS MTA Solution description, as well as a discussion of the actions taken regarding Davis-Besse and Oconee 1 and 2. (See attached).

In completing this MPA, the applicable Project Managers will be provided with the correct SE Input Date and/or Imposition Completion Date, as appropriate, and will be requested to update their SIMS reports to reflect the correct dates.

Finally, as adequate procedural guidance has been reviewed and approved for the various owners' groups and has been determined to be sufficient to mitigate any consequences of void formation, review of plant-specific emergency operating procedures through regional performance of TI 2515/86 is not necessary. Hence, the staff recommends that the regions be ,

immediately informed that they should discontinue performance of TI 2515/86  !

and this TI should be cancelled. Cancellation of verification of the completion of this MPA should be reflected likewise in the SIMS MPA solution description (see attached) and the verification complete date ,

should be made N/A for any plant at which TI 2515/86 has not been l completed. '

Critifl!!pd b7 Ofiifr.d sfp ed h M.W. Hodges, Chief Robert A. Capra, Director Reactor Systems Branch Project Directorate I-1 Division of Engineering and Division of Reactor Projects, I/II l Systems Technology l

Enclosure:

As stated l

PDI-1 g PDI-1xi/M CVogan SMcNeil:mak MWHodges . apra  ;

6/10/28 6/l0/88 6/ It/88 6/jp/88 l

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R-1216310-MPA SYSTEM PACE 5AFETY ISSUES MANAGEMENT 1 MPA SAFETY ISSUE LEVEL INFORMA MPA NUMBER: B-66 TITLE: NATURAL CIRCULATION C00LDOHN CONTACT: 5. MCNEIL TYPE: MPA IDENTIFYING ORGANIZATION: NRR STATUS: ComPLE1E SPONSORING OFFICE: NRR PRIORITY: M TYPE OF REACTORS AFFECTED: fid8 OTHER:

DESCRIPTION SOLUTION (NEAR AND LONG TERM)

MPA PROBLEM BACKGROUND E:: Z - ^. - C""E M ..;;;TICA ;oa JN I T e htL'/ coNisDewe0 sie ST. LUCIE UNIT 1, HHILE COOLING DOHN ON NATURAL GENERIC LETTER 81-21, ISSUED MAY 5, 1981, REQUESTED: Soi CIRCULATION DUE TO A COMPONENT COOLING HATER 1. A DEMONSTRATION THAT NATURAL CIRCULATION C00LDOHN MALFUNCTION, DEVELOP.fD A STEAM SPACE IN THE UPPER BY PROCEDURE SHOULD NOT RESULT IN REACTOR VESSEL VOIDING, HEAD OF THE REACTOR VESSEL. CORE COOLING HAS NOT 2. A VERIFICATION THAT SUPPLIES OF CONDENSATE GRADE LOST, HOWEVER, THE COMPLEX SITUATION HAS DEEMED AN AUX FEEDHATER ARE SUFFICIENT, AND UNDESIRABLE CHALLENGE TO THE OPERATOR. ALL PHRS 3. A REVIEH OF ASPECTS OF TRAINING AND PROCEDURES HERE REQUESTED TO REVIEH PROCEDURES FOR PLANT C00LDOHN DEALING HITH THIS 0;;00L; SUBJECT. vorbitK ON NATURAL CIRCULATION TO DETERMINE IF VOIDING HILL f0^."LI""C" F0" "??'_ GAVC OC % g CT vehi "lL IC"*Jabuel)

^.,;;CD BY NRR f+# en OCCUR IN THE REACTOR VESSEL. IN VERIFYING LICENSEE COMPLIANCE HITH BIP RSB 5-1, COMMENTS " "DESIGN REQUIREMENTS OF THE RESIDUAL HEAT REMOVAL SYSTEM",

THERC IS A 9060 . 00SILILI!7 !;iC REGIGN.i TiA7 iiAVC ALRCA07 LOOXCO AT !" "20CEOU".EC. OF THE STANDARD REVIEW PLAN, 8M LE "*I' tr> T H E ." L A " ' ~r -G UJ O" r*t surt -S PEC# r SAFE,TY.

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g b IIgFs roY A{1h 66 f6PFOA M D Til AU " G li yh CcHDtAcTIAIG 7( l1 S o S /f f,, V 58; D. NEED FOR VERIFICATION: suf 5Eq worrl'/,Rgnc,09 SYs'1 EMS 64 AAltra $'Aff E d ( Utn*0 r) OF 6 FYiG NEEDED OFFICE of v erbrH&. DETEENINSD T11/p .y pgasse smetGgacy PWOC&RI (YES/NO) RESPONSIBLE y y pc5g,g ppn9, g 79 pyypq497y yo;nygg gpyg(q g y gy,$

VERIFICATION. . . . . . . -VES- --

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5. REQUIREMENTS IMPLEMENTATION BY LICENSEE AND VERIFICATION BY NRC (,c/vE #f t OidNE#5 ga@ospd Gu rD ANCe H AS 56e.

COMPLETION DATE OF A&vggweD AN() /):op#0 065) by N K 4, s7A ff STATUS (PLANTS) LAST PLANT IMPOSITION. . . . . . . . . . 48 0F .9&N T E J00 I N NOMu@ Gu'Dg5 [24 vi b f D /)Dt:Qu KI6 IMPLEMENTATION. . . . . . . .if7 R OF 5 TNT 00/90 /)S S i( 44NCG OF g/ O tt ) C-F FE (75 M' 7 'G E* 'O M '

VERIFICATION. . . . . . . . . 14 0.C 'M i{-9 06/88 Tf}sgeFORE, Ve d it:rms:Otl T!!!0 !Gli f6W* fN OF TT 9'ild % W3 CMC & L L G b .

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SAFETY ISSUES MANAGEMENT SYSTEM PAGE 2 MPA SAFETY ISSUE LEVEL INFORMA PiPA NUMBER: B-66 TITLE: NATURAL CIRCULATION C00LDOHN

(. REQUIREMENTS IMPLEMENTATION BY STAFF A. STAFF REQUIREMENTS -- TI 2515/86 - C ant t llE h COMPLETION DATE: N/A 0FFICE(S) RESPONSIBLE: NfA B. ROUTINE INSPECTION PROGRAM MODIFICATIONS: MODIFICATIONS NEEDED (YES/NO) NO MODIFICATION COMPLETION DATE: N/A M0DIFICATION TEXT NMM NO MODIFICATION TEXT FOR ISSUE NMM I

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O[ l[/M[88 h h n A b ,A & et vio a L[% MO I"y UN DAT 03/15 m SAFETY I5 SUES MANAGEMENT SYSTEM PAGE 3 PLANT LEVEL INFORMATION MPA NUMBER: B-66 TITLE: NATURAL CIRCULATICH C00LDOHN DOCKET IMPOS RAI SE IMPOS IMPLEM VERIFY PLANT JAC 8 PRIORITY _INIT RAI RESPONSE TER INPUT @MPL ET @ MI L E COMELE RKANSAS 1 M4/181 M 05/81C 07/11/85C 07/85C 07/85C 03/88 RKANSAS 2 M47161 M 05/81C 03/27/84C 03/84C 03/84C 09/87C EAVER VALLEY 1 M47146 M 05/81C 08/12/83C 08/83C 06/84C 00/00C ALVERT CLIFFS 1 M47158 M 05/81C 07/08/83C 07/83C 07/83C 10/87C ALVERT CLIFFS 2 M47159 M 05/81C 07/08/83C 07/83C A7/8;C 10/87C 00K 1 h47164 M 05/81C 12/09/83C 11/83C 00/83C 00/84C 09K 2 M47165 M 05/81C 12/09/83C 11/83C 00/83C 00/84C RYSTAL RIVER 3 M47166 H 05/81C 04/23/84 N/A 06/20/86C 06/86C 12/85C 01/88 AVI3-BESSE 1 M47182 M 05/81C 12/87 02/85C 02/88 lIABLO CANYON 1 M51994 07/83C 07/00/84C 07/84C 03/85C 07/87C lARLEY 1 M47172 M 05/81C 11/15/83C 11/83C 00/00C 04/88 lARLEY 2 M47173 M 05/81C 11/15/83C 11/83C 00/00C 04/88 iORT CALHOUN 1 M47180 M 05/81C N/A 10/28/83C 10/83C 02/84C' 12/87

!INNA M47176 M 05/81C 04/22/83C 04/83C 11/81C 06/88 lADDAM NECK M47171 M 05/81C 07/26/83C 07/ 07/83C 12/87

NDIAN POINT 1 M47177 05/81C 06/22/84C Al N/A N/A
N3IAN POINT 2 M47156 M 05/81C 08/01/83C 08/ 3C 10/85C 03/88

,NDIAN POINT 3 M47178 M 05/81C 06/10/83C 06/83C 10/85C ;1/87N

E 4AUNEE M47160 05/81C 08/15/83C 08/83C 08/83C 08/83C lAINE YANKEE M47174 M 05/81C 05/31/83C 05/83C 00/83C 02/88

'u3UIRE 1 M51644 05/83C 09/30/84C 09/83C 00/83C 04/88

C 3UIRE 2 M51645 05/83C 09/30/83C 09/83C 00/83C 04/88

,I.LSTONE 2 M47149 M 05/81C 06/22/84C 11/81C 11/81C 03/88

.0tTH ANNA 1 M47152 M 05/81C 10/19/83C 10/83C 10/83C 03/88N

.0tTH ANNA 2 M47155 M 05/81C 10/19/83C 10/83C 10/83C 03/88

C ) NEE 1 M47183 M 05/81C 04/23/84 06/14/85C 06/85C 00/90 04/88 C) NEE 2 947184 M 05/81C 04/23/84 06/14/85C 06/85C 00/90 04/88 CINEE 3 M47185 M 05/81C 04/23/84 06/14/85C 06/85C 01/84C 04/88

-. . I S A DES M47186 M 05/81C 12/15/83C 12/83C 12/83C 09/87C

- { NT BEACH 1 M47147' M 05/81C 11/08/83C 11/83C 00/81C 11/87N JINT BEACH 2 M47148 M 05/81C 11/08/83C 11/83C 00/81C 11/87N 01IRIE ISLAND 1 M47150 M 05/81C 07/18/83C 07/83C 07/83C 10/87 ,

1\IRIE ISLAND 2 M47151 M 05/81C 07/18/83C 07/83C 07/83C 10/87 1

?;4CHO SECO 1 M47170 M 05/81C 05/15/86C 05/86C 05/86C 03/88 I 3IN50N 2 M47175 M 05/81C 09/27/83C 09/83C 11/81C 04/88 l 4.EM 1 M47162 M 05/81C 08/15/83C 08/83C 00/82C 05/87C i 1.EM 2 M47165 M 05/81C 08/15/83C 08/83C 00/83C 00/83C T8 ONOFRE 1 M47169 M' 05/81C 08/09/83C 08/83C 08/83C 03/88 s 1 0"Or2C 2 M6284", -12/85C 12/95/97 et/su tf/65C o 'voo -- 1 H NOFRC 3 M6 28 49 -- - ----12/8 5C~ - -- - - - - - - - 12/31/87 01/88----12/MG-8&44-JUDYAH 1 M51789 06/83C 12/30/83C 12/83C 10/84C 10/87C 23:10YAH 2 M51790 06/83C 12/30/83C 12/83C 10/84C 10/87C LUCIE 1 M42252 H 06/80C 05/06/83C 04/83C 00/83C 02/88

? -1216310-MPA RUN DATE: 03/1h8 SAFETY ISSUES MANAGEMENT SYSTEM PAGE 4 PLANT LEVEL INFORMATION trA NUMBER: B-66 TITLE: NATURAL CIRCULATION COOLDOHN DOCKET IMPOS RAI SE IMPOS IMPLEM VERITY PLANT TAC 8 PRIORITY INIT RAI RESPONSE TER INPUT COMPLET C_Off!1El (Qf1P_L EI

>JRRY 1 M47167 M 05/81C 10/19/83C 10/83C 09/86C 04/88

% JRRY 2 M47168 M 05/81C 10/19/83C 10/83C 09/86C 04/88

.iEE MILE ISLAND 1 M47157 M 05/81C 06/22/84C 06/84C 07/85C 12/87 10JAN M47179 M 05/81C 08/12/83C 08/83C 08/83C 10/87C IRKEY POINT 3 M47154 M 05/81C 08/05/83C 07/83C 00/83C 04/88N iRKEY POINT 4 M47155 M 05/81C 08/05/83C 07/83C 00/83C 04/88N LHKEE-ROHE 1 M47145 M 11/81C 10/25/83C 10/83C 10/83C 12/87N c.ON 1 M47187 M 05/81C 08/09/83C 08/83C 00/85C 03/88

/_ ION 2 M47188 M 05/81C 08/09/83C 08/83C 00/85C 03/88 e

_ - _ _ _ _ .