ML20211G656

From kanterella
Jump to navigation Jump to search
Allegation Review,
ML20211G656
Person / Time
Site: Maine Yankee
Issue date: 12/18/1995
From: Collins T
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20211G606 List:
References
FOIA-97-154 NUDOCS 9710030149
Download: ML20211G656 (11)
v • d • e


Text

4 MAINE YANKEE ALLEGATION REVIEW TIMOTHY E. COLLINS REACTOR SYSTEMS BRANCH DIVISION OF SYSTEMS SAFETY AND ANALYSIS

. DECEMBER 18, 1995 m,m. ,_

BARRY97-154 PDR

//p}ejh

'x (f

l ALLEGATION.

SUMMARY

ECCS INADEQUATE FOR OPERATION AB0VE 2400 MWt

- POST-TMI MODEL EXCEEDS PCT LIMITS

- BEST ESTIMATES USED IN PLACE OF APP K CONTAINMENT INADEQUATE ABOVE 2400 MWt

l STAFF REVIEW FINDINGS TO DATE TECHNICAL ISSUES:

  • ECCS ANALYSES QUESTIONABLE:

MODEL UNSTABLE DURING SIT INJECTION

- PCT OSCILLATIONS BREAK SPECTRUM ANALYSIS T00 LIMITED

- NO ANALYSES.AB0VE .35 SQ FEET

- SATISFACTION OF CODE SEF, CONDITIONS UNCLEAR

  • CONTAINMENT ANALYSES SHARPENED CONSIDERABLY MANY CONSERVATISMS REMOVED FROM ORIGINAL ANALYSES REVISED METHOD GIVES RESULTS WITHIN DESIGN LIMITS REVISED ANALYSIS NOT ANALYSIS OF RECORD o

3

-amu 4e' u.44ql.u aiiimmiuimm ie a un.puusi eau 4xiuppmuu . m STAFF FINDINGS TO DATE (CON'T)

PROCESS ISSUES:

  • ECCS MODEL CHANGES MADE WITHOUT STAFF APPROVAL TMI REQUIRED ECCS ANALYSES NOT SUBMITTED 50.46 REPORTING REQUIREMENT NOT MET MODEL CHANGE GREATER THAN 50 DEGREES
  • CONTAINMENT LICENSING ANALYSIS NOT CURRENT
  • DOCUMENTATION PRACTICES POOR 4

STAFF ACTION PLAN SHORT TERM:

DEFINE CYCLE 15 POWER LEVEL FOR WHICH 50.59 REVIEW CLEARLY SHOWS THAT PREVIOUS CYCLE BASED UPON CE METHODS IS BOUNDING

- MUST ADDRESS II.K.3.30 REQUIREMENTS

- MUST ADDRESS SLEEVING IMPACTS

- MUST CONSIDER CONTAINMENT MAY REQUIRE SUBMITTAL FROM YANKEE TO CHANGE TS AS NEEDED TO ASSURE OPERATING LIMITS ARE BOUNDED BY PREVIOUS CYCLE ORIGINAL LICENSING BASIS-0F 2440 MWt IS TARGET

- CONSERVATISM NEEDED TO DUE COMPLEXITY OF REVIEW AT HIGHER POWER LEVELS 5

i L' STAFF-ACTION PLAN (CON'T)

LONG TERM (SEVERAL MONTHS): .

t REVISIT APPROVAL OF RELAP5YA FOR SMALL BREAKS

- REVIEW II.K 3.31 CLOSE0VT 4

PERFORM INDEPENDENT ANALYSES OF MAINE YANKEE INCLUDING LARGER THAN 0.35 FT**2 BREAKS ADD YANKEE TO LIST FOR BROAD AUDIT REVISIT TMI II.K.3.31 TO CONFIRM SUBMITTALS FROM OTHER I.ICENSEES ADDRESS PROCESS ISSUES

- LICENSEE COMMITMENTS TRACKING

- DOCUMENTATION / REPORTING ISSUES 6

D%

g StAL uk P L. TEI 41 - 41 " ~ ^'102 I" * *

      • g\ -

I s u=rne men.

NUCLEAR AEOULATORYCOMMstgCN

(. WASMNSTON.8.C.asegg h

4 PAC 8tMfLE TRANSMtSSION DATE: - -

L Th)

PAX No.:

g g,, 'e G

U.S. NUCLEAR REQULATORYCOMMIS$10N QPPICE OF NUCLEAR REACTOR REGULATION (301)

PAXNo.: 415-2102 TELNO:

PAGS1OP PA058 '

r

'l

% #( - \

a

. ~ . * -h 9

. c 5

Maine Yankee Candaterred Analysis Licensing Basis Dwisynon Blowdown /Reflood Blowdown Recood Peak-Penalty Peak (aaig)

@sko (psis) -

ca : = swEc A :,.;, '

RCS L--s&-o Increase 4g 5 _

[c SWF to 550P 1.0/1.0 '

50.5 -

Uprate to 2630 MWt v 0.2/0.2 50.7 50.0 hmalErio.rion of RCS $.

o 3jo,g 53,5 So,g E Containment Volume (1.825E6 ft8) 1.8/2.9 53.3 53.7 Containment Spray Flow Reduction .

I Jacrease in Containment Temperature (1857 to 1127)

RCS Tempermeure Increase (550P to 552P) .

e Spray Effectivcoess Delay ]"

R Contalanent Initial Pressure sacrease fmm 0.8 em 1.5 pelge ' -

~

e Uprate so 2700 mit 0.2/0.2 53.5 53.9 -

, u N

a.

m PRELIMINARY h m

,O

=M t

g. .. ,

? ...

i.

CHRONICLE OF SMALL BREAK LOCA A h fSES AND 11.K.3.31 ISSUE FOR MAINE YANKEE FUEL CYCLE / YEAR EVENT COMMENT 3 Sept. 22, 1977 Submitted original The analysis was performed basis to NRC on small using Combustion Engineering's break loss of coolant small break Evaluation Model accident analysis described in CENPD-133, "CEFLASH-4HS Computer Code for Reactor Blowdown Analysis of the Small Break Loss-of-coolant Accident." August 1974 (Maine Yankee letter, WHY-77-07 dated 9/22/77) 5- November 21, 1980 NRC Action Plan Item Identification of RELAP4 or RELAPS II.K.3.30, Revised option (Maine Yankee letter to NRC, Small Break LOCA Method JHG-80-1061, WM4-80-153, dated 11/21/80) 6' December 16, 1981 NRC Action Plan Item Notification of selection of RELAPS lik.3.30; Revised Option (letter Maine Yankee to NRC Small Break LOCA Method FMY-81-181, dated 12/16/81)

-7 January 14, 1983 RELAP5YA Computer rogram u Submittal of REL k5Y yor' approval, to analyze BWR Ful Break (Tanke~e Atomic Electric Comp:ny to Spectrum and PWR Small NRC, FYR-83-9, dated 1/14/83)

Break Spectrum 7 March 14, 1983 NRC order- Required MY to submit the plant specific SBLOCA--(II.K.3.31) within one year after the staff approval of generic methods (ll K.3.30).

7 -April 9, 1984 II.K 3.5 - RCP trip MY submitted YAEC-1423 that documented the analysis for RCP trip,by using RELAP5YA to address the ll K.3.5 requirements 8 June 20, 1985 Conditional Acceptance In response to THI Action item for referencing of II.K.3.30, Combustion Engineering licensing topical report Owners Group (CEOG) has elected to CEN-203(p), " Response to justify the continued acceptance-of NRC Action Plan item the CEFLASH-4AS computer program II.K.3.30 Justification for small break LOCA analysis or of small break LOCA evaluation. (NRC letter-to CE Methods." Owner Group - Northwest Utilities, 6/20/ .

i A

j l

0-i .. 9 April 15, 1986 Closure of II.K.3.5 NRC letter to MY stated that the l analysis (using RELAP5YA to

! determine the RCP trip strategy) is l acceptable to close out II.K.3.5 l

9 February 11, 1987 Acceptance for refere':ing NRC staff found TMl Action item of licensing topical report II.K.3.30 & 31 to be resolved for all licensee Combustion Engineering plants (NRC letter to Combustion Engineering Owners Group)

-10 December 7, 1987- TMI Action Item II.K.3.30 Maine Yankee attempted to close out II.K.3.;I vxe. w g e " M d w!!.K.3.30 and ll.K.3.31 ork. (Maine usingtoCEOG Yankee letter NRC,

, ,/,gpr ge gr-r4 ,t! /M C MN-87-134, 12/7/87).

.. - N 11, January 30, 1989 ' ' Acceptance for Referencing J RC C1oseout of II.K.3.30-(NRC

"' Topical Report .YAEC-1300P, (NRC letter to Maine Yankee dated Volume 1, 2, 3, "RELAPSYA: 1/30/89)

"A computer program for Light Water Reactor System Thermal Hydraulic Analysis" 11 January 23, 1989 THI Action item !!.K.3.31 YAEC licensing analysis nf small break LOCA scenarios for the Yankee Nuclear Power Station converted of a limited evaluation s model analysis augmented by Best-Estimate Analyses.

11 February 2, 1989 NUREG-0737, item II.K.3.31 NRCAcceptanceinregarJingto plant specific calculations ll.K.3.51 for Yankee Roe (NRC to show compliance with (NRC letter dated 2/2/89) 10 CFR 50.46 d ll Q y 8, 1989 - - ~ '

Maine Yankee: Implementa- NRC closed item tion of Small Break LOCA II.E.3.31 for Maine Yankee (NRC analysis NUREG 0737 letter to Maine Yankee dated ll.K.3.30 and II.K.3.31 5/8/89 h n f % f r -

(Tag 48176) in .,-

11 December 19, 89 (File SEN-89-38) Telecon "I indicated to Eric' that we have between NRC (G.D. Whittier) are re-priorized our Small Break and Maine Yankee LOCA work and now plan to have the (S.E. Nichols) the ll.K.3.31 reviews done by June 1, 1990. I indicated this meets P. Sears' letter of May 8, 1989, and that we no longer need to send them a ll.K.3.31 schedule.

He agreed."

12 January 2, 1990 Maine Yankee Management MY file 90-0037 memo between agreed to use RELAP5YA BE/EM P.L. Anderson & W.J. Metevia for ll.K.3.31 SBLOCA analysis

5 12 June 1, 1990- RELAPSYA BE/EM used Maine Yankee letter indicated that for Maine Yankee-SBLOCA the SBLOCA analysis is complete (Licensee internal memo between P.L. Anderson & R.K. Funderame) 12 August 1, 1990 M/engineeringdept.

Licensee internal memo betwe /en delivered ll.k.3.31 SBLOCA P.L. Anderson & R.K. Sunddra analysis using RELAP5ya BE/EM (File LOCA 90-110) to its licensing dept.

14 June 1993- SBLOCA Analysis using This analysis was used RELAP5YA EM model was issued to support Cycle 14 reload and satisfy ll.K.3.31 requirements I

i 1

.~ .

//p/:-Iny.

I. . [\ . f .....JVCLEAR REGULATORY Coswissum .

usemo stuu f [m y' M /

4 y

.w .... . . . ...

== === m ,ete.amee

narch'1e,-1ssa v.e. - 8t. . ' ~

..4 .. ...-

. . .y - - - "

M Fut:- R. NESSnUt

! FIDt: P. SEAR $'

SUBJECri- SlpeWrY OF METIM HELO ON FE8RUARY 2,1988-CONCEltNING -

. LOCA CODE ' COMBUSTION .~~ .

ENGINEERING SMALL R..

The~ meedng ~was held at One Whtte #11st horth in 1tocht116 Maryland. Those who i

attended are Itsted in the Enclosure. . .

- . ., .'Condiistion Engfneer'fng, Mef ne Yant.ee't. diasu'Itant,' dis'eussed the.applicabfl f ty i

-of CEE203-P Revisfon (11-P. , f 4sponse to NRC Action Plan ! test II.'K.3.30

'~'Justiftc4 tion of Small Ersak LOCA Methods." Tn that discussion, slidee were j used.that were submitted by letter dated February 1,1908 from Combustion Engineerteg, Inc. to NNC.

l

  • - The staff expresse'd reservations about thesa 9eceraf areas of'th'e compIster moeel to be used

in the Small peak LOCA dode. Those reservations are as followst'

.. z. .. ,. - '. .

4 1..," Sas_generatton.fo5 the stmas.generAtte, degradation effects must be i

shown'.to be, cas$erable between Main Yankee and the .Stendard Combost4on Engineering .P1 art. -- -

{ -

'~-

j  ;- ,' .1. ' The ffect. of, the df chaije andel mus't be .dhcos's'ed.P

[ .' - -

~ ~ ' '53 Yleerua') non,_-gqvt fibefus' treatdent di.rfag Safety injection /15 i . ' .. conservative fh-~fJie TtamtrTT.ombuttion Engineering Plant mcdel;-

4 but fior the Ma fne Yankee model f t1ts not. The model proposed must

- be shown tb he idequate or conservatt.ie per the Nguirements'lof 1 .-

'!!.X.'.33.of Nurth-0737 Extrapolation and hand calculations. to

  • account for' use of.a sort-con'servettve..cbaputer model' on Maine 'Yan.kee'

$pacift'c problaims is .not acceptable to the staff.. -" -

' ' ~

hbm i -

'~. ,

Patrick Sears, Prwject Manager.,

'- ~

Project Ofrectorate I,3 1 c . ._ , . , .

. Div.fsinri of Reactor PrcJ,ects. t/f f- -

).

. c. . -

' Enclosure ' .

'GPONSIBUtTT.g_'jh*

i -. - '-

l

,i --

1 '

. . 4'. . .

'f.

, ' MstOND BY '.

DUE DATE - 0 1",

' f' i

"/

l

~

- y- - s

. .,
Retrieved from "https://kanterella.com/w/index.php?title=ML20211G656&oldid=3275407"