ML20203C235: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:-.    .    .    .      -                -                            .          - -
          .                                                            February 4, 1999 LICENSEE:            Duke Energy Corporation FACILITIES:          McGuire Nuclear Station, Units 1 and 2
 
==SUBJECT:==
MEETING
 
==SUMMARY==
- MEETING OF JANUARY 27,1999, REGARDING SOLUBLE BORON AND BORAFLEX On January 27,1999, the staff met with Duke Energy Corporation (DEC) personnel to discuss information related to a proposed license amendment to take credit for soluble boron and partial credit for boraflex in the spent fuel pools at the McGuire Nuclear Station. The meeting was scheduled at the request of DEC to present its general analytical approach and provide an opportunity for staff's questions.
DEC plans to use two computer codes in its assessments. The BADGER Code would be used to measure boron and the RACKLIFE Code to predict boraflex degradation. Also, DEC plans to test for available boraflex using neutron blackness testing every 3 years. The staff indicated that the review and approval of credit for boraflex is a first-of-a-kind that will require additional time than just the approval for soluble boron.
Enclosure 1 lists the meeting participants. Enclosure 2 is the handout provided by DEC.
Fianbinaldi,Ncij00tNrfager Project Directorate 11-2 Division of Reactor Projects - t/ll Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-70                  Distribution:
See next page                                                          l
 
==Enclosures:==
l
: 1. Meeting Attendees
: 2. DEC Handout I
cc w/encis: See next page Q              l l
l
' Ta receive a copy of this document, indicate in the box: "C" = Copy'without attachment / enclosure "E" = Copy with attachment / enclosure "N" = Nosopy OFFICE PM:PDil-2ojl              LA:PDil-2)        D:PDil-b      _
                                                                                                                                  )
NAME        FRinaldi:W LBerry, AG HBerkcJ/
DATE      7 / 61 / 9 9          4 /D/99    i Q/ /159              / /99            / /99                  / /97 DOCUMENT NAME: G:\MCGUIRE\MTG,WPD OFFICIAL RECORD COPY                                                                          ,
                                , , ,, a e 9902110288 990204 DR    ADOCK 05000369                                                                    , , , , , ,
r la L , --                          -  -
 
    ,          kE Cl4 g              S1-                              UNITED STATES g
2 j              NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2068H001 o%            8                                                February 4,                1999 f*****f LICENSEE:          Duke Energy Corporation FACILITIES:        McGuire Nuclear Station, Units 1 and 2
 
==SUBJECT:==
MEETING
 
==SUMMARY==
- MEETING OF JANUARY 27,1999, REGARDING SOLUBLE BORON AND EORAFLEX
 
==REFERENCES:==
Meeting Notice by F. Rinaldi, dated January 11,1999 On January 27,1999, the staff met with Duke Energy Corporation (DEC) personnel to discuss information related to a proposed license amendment to take credit for soluble boron and partial credit for boraflex in the spent fuel pools at the McGuire Nuclear Station. The meeting was scheduled at the request of DEC to present its general analytical approach and provide an opportunity for staff's questions.
DEC plans to use two computer codes in its assessments. The BADGER Code would be used to measure boron and the RACKLIFE Code to predict boraflex degradation. Also, DEC plans to test for available boraflex using neutron blackness testing every 3 years. The staff indicated that the review and approval of credit for boraflex is a first-of-a kind that will require additional time than just the approval for soluble boron.
Enclosure 1 lists the meeting participants. Enclosure 2 is the handout provided by DEC.
                                                          "p~w AC                                  Wr Frank Rinaldi, Project Manager Project Directorate ll-2 Division of Reactor Projects - 1/Il Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-70
 
==Enclosures:==
: 1. Meeting Attendees
: 2. DEC Handout cc w/encis: See next page I-l
 
,.''.                                                                                                              1' l                  McGuire Nuclear Station
!                  cc:
l                  Ms. Lisa F. Vaughn                                Ms. Karen E. Long i-                Legal Department (PBO5E)                          Assistant Attorney General
!                  Duke Energy Corporation                            North Carolina Department of I                  422 South Church Street                            Justice Charlotte, North Carolina 28201-1006              P. O. Box 629
                .                                                    Raleigh, North Carolina 27602 l                  County Manager of
;                    Mecklenburg County                              L. A. Keller 720 East Fourth Street                            Manager- Nuclear Regulatory Charlotte, North Carolina 28202                    Licensing Duke Energy Corporation                      {
MichaelT. Cash                                    526 South Church Street                    -1 Regulatory Compliance Manager                      Charlotte, North Carolina 28201-1006          l l:                Duke Energy Corporation
                . McGuire Nuclear Site      .
Regional Administrator, Region il            i 12700 Hagers Ferry Road                            U.S. Nuclear Regulatory Commission          !
Huntersville, North Carolina 28078                Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 J. Michael McGarry, lil, Esquire                  Atlanta, Georgia 30303                      i Winston and Strawn                                                                              i 1400 L Street, NW.                                Elaine Wathen, Lead REP Planner              i
                . Washington, DC 20005                                Division of Emergency Management 116 West Jones Street Senior Resident inspector                          Raleigh, North Carolina 27603-1335            ;
c/o U.S. Nuclear Regulatory Commission                        .
i 12700 Hagers Ferry Road                            Mr. Richard M. Fry, Director                !
              - Huntersville, North Carolina 28078                  Division of Radiation Protection              -
North Carolina Department of
              - Dr. John M. Barry                                    Environment, Health and Natural
              - Mecklenberg County                                    Resources                                    !
p                  Department of Environmental                        3825 Barrett Drive Protection                                        Raleigh, North Carolina 27609-7721 700 N. Tryon Street Charlotte, North Carolina 28202                    Mr. T. Richard Puryear Owners Group (NCEMC)
Mr. Steven P. Shaver                              Duke Energy Corporation L                  Senior Sales Engineer                              4800 Concord Road Westinshouse Electric Company                      York, South Carolina 29745
              ' 5929 Camogie Blvd.
Suite 500                                          Mr. H. B. Barron
!                  Charlotte, North Carolina 28209                    Vice President, McGuire Site L                                                                    Duke Energy Corporation i                                                                    12700 Hagers Ferry Road Huntersville, North Carolina 28078
[
i y
 
                .                                                                                        l
                                                                                                          )
1 i
                  ' Distribution for Meetina Summary dated February 4, 1999 E-MAIL -                                  . HARD COPY                              $
                    . S. Collins /R. Zimmerman                  Docket File                              1 B. Boger -                                  PUBLIC                                  i J. Zwolinski                                PDil-2 Rdg.                              l H. Berkow                                  F. Rinaldi                              1
:I.. Ber:y                                    OGC                                      !
L Kopp                                      ACRS D. Jackson K. Parczewski
                  . C. Lauron M. Tschiltz, EDO L Plisco, Ril C. Ogle, Ril l
J    e,
                                                  .J i
1 l
I l
l
: l.                                                                                        :
l-i
 
    .        .                                                                                                  l 6  .
                                                                                                                  )
i
;.~
l l
l LIST OF PARTICIPANTS MEETING WITH DUKE ENERGY CORPORATION FEBRUARY 4.1998 NAME                    . AFFILIATION Frank Rinaldi            NRC/NRR/ Project Directorate ll-2 l                  Mike Cash                Duke Energy Corporation, Regulatory Compliance                        I Julius Bryant            Duke Energy Corporation, Regulatory Compliance L                  Keith Waldrop            Duke Energy Corporation, Fuel Management / Criticality Paul Guill              Duke Energy Corporation, Nuclear Engineering Gary Walden              Duke Energy Corporation, Nuclear Engineering l                  Jimmy Glenn              Duke Energy Corporation, Nuclear Engineering L
                . Diana Jackson            NRC/NRR/ Plant Systems Branch Kris Parczewski          NRC/NRR/ Materials and Chemical Engineering Branch
: j.              - Carolyn Lauron            NRC/NRR/ Materials and Chemical Engineering Branch Larry Kopp              NRC/NRR/ Reactor Systems Branch i
!                                                                                                                  1 i
j j
l i
I '
j ,,
l-h Enclosure 1
          ,                  -  ,    .                                      =
 
                                                ,*  O  ,,
EdPower.
a o+r- ac .,,
                                                  .            t Management of Boraflex Issues                            l at McGuire Nuclear Station L
XRC Meeting 4
January 27,1999                              1 5:
4 Enclosure 2
 
s'  e        >
EnDuke                                                                '
C#-Power,      c.,                          Meeting Purpose                a u
:i
* Review status of Boraflex degradation and      ,
subsequent corrective actions; Review and discuss proposed Technical Specification and regulatory commitments.                  o i
li I
2 5
 
        !  l        , I  t :!      :            :                  :                    .
                                                                                                  ,      i -,
e a                                                4 n                t i
n                          s i
o                U              l e
i l
o 3
t                    o              u          o t
a                  w            Ft i P    .
T              t n nl  u    e1 S                      e              e          u00 r                  s u
ph        F P S c a                h o            d e nn e r e a  t o
e                  g            t            pi g l                      n              a oS c                i t
Ri dcf lo hc r e
u                  s ewe                    o a o N                    WP DP Et w e
r                l r*
p                  -
e(p-    e i                                                                s u
J                                      4
{d                          _/Mn      wq$
g{he+;S;g$k,F y
                                                        -                        e.(
                                                                  '+                            s v.
c4 a G                    hd,exdj f            41                    -                              -
h          cf t
f~
                                                                              .^ +,.
c                              i kh%n$wf i
l E          @
M                    hJ E$m,~mT'
                                            'sM a
                                                                                  ~-
y.
M
                                  $$m:~    a wn
: c.            $M=x:      1~
E mfr    b'    -
                                  $fw?p M
w@e                            sn?g
                                                                          .W g$',m=.
l 2$
ye,D h
y k        ,t                          O g
h@#ps%;5qa-r s?.Ws                                        "
f)
J s
                                                                                      '2 mmi 1 7
N$+,5W u t
                                  !  $&}j;pmig          .
g
 
    .                                                                                                    .l  -
EllhDuke EdPower.
MNS S E ent Fuel                                                        ~!
          '*"~"
* Pool Overview High deilsity re-rack with Boraflex design in both McGuire units;
* Duke has monitored pools and racks to detect degradation of Boraflex;
* There are indications of Boraflex degradation in both units' racks.
4 3
 
      .                                                                                                                                      e'
* m ouge                                  .
EdPower.
          '~~""~"'
Industry Experience a      Research started in 1987;
* Industry User's Group formed,                                                                                                          ;
Enhanced measurement and computer                                                                                      .
model for monitoring Boraflex health developed in 1996; 5
 
                                                            ?:  .
Duke                                                ";
        #ffE*i.,          McGuire Efforts
* Neutron " blackness" testing in 1991; Duke Power Company has provided responses to 3RC Generic Letter 96-04;
* BADGER demonstration in January 1997;
* Criticality analysis revised; i
A MNS-specific RACKLIFE model was developed to i
assist in assessment of pool degradation;        .
Monitoring pool chemistry.
k
_ -  __- --- __a
 
i!          !        l      .!        .l                i,l    i. +                        i:!
.                                                                                            1(                ! ;
                ~
  .  'o n        "e
-                                                            i g
l b
a 7
s n                                                        r ed          e s      .
o                e r          i nd                    e  pl i                  a            meinOr-                        o
..                                                              r a "t t                  s          d ut                              n                    -
i                l                a s n                    e
-              d                  e n          d e              ni a      r o a c nS              a p;          t e
o      ms      n oN              xd e  e nt e s e ml                    r l i om o d CM t
l f
a r g d
a r      l e o t
r s ns a
e pa h h moa t
nt a            o e                                    oi  t e            Bd            I                cb        Bw r
r                -            ,                        *
.                u          .'            A  ;      Y.        ..              x ;-
C W
                                                        ?<
k
-.                                            y.
r.
                                                      ~^
-                                                                                            c'J ee-s, kw m.
s_
uo                                                                      m DP-
-                                                        5
                                                            .x              y ad' E
                                                      'l, '
 
                                                                                                                                                                                  .      *1 oake yff~"'*l;, MNS Options Considered
* Poison ~ inserts; Restrictive storage patterns; Re-rack Region One;
* Boraflex degradation chemicalinhibitors; Implement WCAP-14416 methodology.
8
_ _ _ - - _ _ _ _ _ . _ - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ - - _ _ - _ _ _ _ _ _ _ _ _ - _ _ .l
 
e l
      .                                                                                                                                                                                                              o-    .  ;
e m oake                                                                                                                                                                                                            =-
CdPower.
          --                                .                                                                                                                                                                                a Option Chosen i
i MNS has chosen to implement WCAP-                                                                                                                                                                                ,
14416 ~ methodology for taking credit for soluble boron in place of degrading Boraflex.
t I
i                                                                                                                                                                                                                            !
c
[
9                        ~
 
i '?
e'  .
O Duke                                                    "
r# Power.
        ~ ~ c.,,
Tech Spec Submittal                        l i
Based on WCAP methodology;
* Criticality analysis indicates current fuel inventories cannot be accommodated using WCAP methodology alone; WCAP methodology does not consider
,-        degrading poison material;
* MXS seeking partial credit for Boraflex.
                                                              ~
10
 
r# Power.
anwcm Pronosed Y        TS Submittal Defines two sub-regions in Region 1:
        - Region 1A (partial Boraflex)
        - Region IB (no Boraflex)
Defines two sub-regions in Region 2:
        - Region 2A (partial Boraflex)
        - Region 2B (no Boraflex)                          -
3 storage patterns in each region:
        - Unrestricted
        - Restricted w/ Filler
        - Checkerboard w/ empty cells New SLC for poison materiallimit; Propose defming sub-regions in Bases.
11
 
      . . . _ _ . . . . . . ___            .m____._                  _ _ . . _ . . _ . _ . . _ _ _ _ . . . . _ _ _ _ _ _ _ _ . . - . _ _ _ _ _ . _ . _ . . _ _ _
i DRAFT SLC Spent Fuel Pool Storage Rack Poison Material -
2 LCO                          The storage rack poison material Boron 10 areal density shall be greater than or equalto:
0.005 gm Bidem' for Region 1 A i                                                          0 gm Bidem' for Region 1B i                                                      0.003 gm Bidem' for Region 2A i
0 gm Bidem' for Region 2B APPLICABILITY:                When a fuel assembly is stored in a spent fuel rack cell, location.
ACTIONS 1
;                                CONDITION                                        REQUIRED ACTION                                                    COMPLETION TIME i
NOTE LCO 3.0.3 ls not applicable.
A.      Spent fuelpool storage rack              A.1        Perform SR 3.7.14.1                                                  1 hour poison materialnot within                                                                                                M
;-                        limit.=                                                                                                                  Once per 24 hours thereafter until affected fuel assembly moved li                                                                M
!                                                                  A.2 Verifyfuelassemblyin affected                                                1 hour
* location meets 3.7.15(b) for Region 1 or 3.7.15(d) for Region 2
)              B.        Required Action and .                    B.1        initiate action to move affected                                      immediately L                        associated Completion Time                          fuel assemblyto acceptable j                        of Condition A not met.                              location i-i  .                                                                                                                                                                                          l r;
            . SURVEILLANCE REQUIREMENTS SURVEILLANCE                                                                                          FREQUENCY SR                  Verify the spent fuel pool storage rack poison material is within                                                    3 years limits.
: e . r. .                  ::- '      -. ,.
                                                                                                                      .a.                                    = = = = - - -      - -
 
l                                                            .      .
i Duke                                                          "
,      Pow-  c ms-xx .,,      Conclusions                                          g l                                                                          .,
1                                                                          ll l                                                                          i Tech Spec Submittal by 2/28/1999; l        Current Operability expires 12/31/1999;                          g l        XRC approval needed by 12/31/1999;                              l Dry Storage to begin in 2000 to provide
!        additional storage capacity;
!        Other options are still under consideration i
for long term resolution.
j                                                      13
 
A--446.-oaso A  - =-&    -  .t.6,a4. MAzoee k & ,4 -4hAA48 4 -U-n A6 -~.bd- d--A+.3iR43 3- 4,s bes-W.,Aere        "n
                                                                                                                    - e.swMe    swn--e,._s-,-m-~Aamoswsn  a  os%misaAe-ms.u-masu.-an,ema--          mmsaw a O
e e
e e;
1 i
i I
e                              M                                                                                                    i CD                                                                                                                                  j oo e-+
M*
M
                            -~- - - -.. .-. . .-.....:. ..- _..-.. = =                          r..        =-.= .
                                                                                                                          - ~ ~ - , - - -                    ,-.                            --}}

Latest revision as of 02:44, 1 January 2021

Summary of 990127 Meeting with Duke Energy Corp Re Proposed License Amend to Take Credit for Soluble Boron & Partial Credit for Boraflex in Sf Pools at McGuire Nuclear Station. List of Attendees & Handouts Provided by Duke Encl
ML20203C235
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 02/04/1999
From: Rinaldi F
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9902110288
Download: ML20203C235 (19)


Text

-. . . . - - . - -

. February 4, 1999 LICENSEE: Duke Energy Corporation FACILITIES: McGuire Nuclear Station, Units 1 and 2

SUBJECT:

MEETING

SUMMARY

- MEETING OF JANUARY 27,1999, REGARDING SOLUBLE BORON AND BORAFLEX On January 27,1999, the staff met with Duke Energy Corporation (DEC) personnel to discuss information related to a proposed license amendment to take credit for soluble boron and partial credit for boraflex in the spent fuel pools at the McGuire Nuclear Station. The meeting was scheduled at the request of DEC to present its general analytical approach and provide an opportunity for staff's questions.

DEC plans to use two computer codes in its assessments. The BADGER Code would be used to measure boron and the RACKLIFE Code to predict boraflex degradation. Also, DEC plans to test for available boraflex using neutron blackness testing every 3 years. The staff indicated that the review and approval of credit for boraflex is a first-of-a-kind that will require additional time than just the approval for soluble boron.

Enclosure 1 lists the meeting participants. Enclosure 2 is the handout provided by DEC.

Fianbinaldi,Ncij00tNrfager Project Directorate 11-2 Division of Reactor Projects - t/ll Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-70 Distribution:

See next page l

Enclosures:

l

1. Meeting Attendees
2. DEC Handout I

cc w/encis: See next page Q l l

l

' Ta receive a copy of this document, indicate in the box: "C" = Copy'without attachment / enclosure "E" = Copy with attachment / enclosure "N" = Nosopy OFFICE PM:PDil-2ojl LA:PDil-2) D:PDil-b _

)

NAME FRinaldi:W LBerry, AG HBerkcJ/

DATE 7 / 61 / 9 9 4 /D/99 i Q/ /159 / /99 / /99 / /97 DOCUMENT NAME: G:\MCGUIRE\MTG,WPD OFFICIAL RECORD COPY ,

, , ,, a e 9902110288 990204 DR ADOCK 05000369 , , , , , ,

r la L , -- - -

, kE Cl4 g S1- UNITED STATES g

2 j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2068H001 o% 8 February 4, 1999 f*****f LICENSEE: Duke Energy Corporation FACILITIES: McGuire Nuclear Station, Units 1 and 2

SUBJECT:

MEETING

SUMMARY

- MEETING OF JANUARY 27,1999, REGARDING SOLUBLE BORON AND EORAFLEX

REFERENCES:

Meeting Notice by F. Rinaldi, dated January 11,1999 On January 27,1999, the staff met with Duke Energy Corporation (DEC) personnel to discuss information related to a proposed license amendment to take credit for soluble boron and partial credit for boraflex in the spent fuel pools at the McGuire Nuclear Station. The meeting was scheduled at the request of DEC to present its general analytical approach and provide an opportunity for staff's questions.

DEC plans to use two computer codes in its assessments. The BADGER Code would be used to measure boron and the RACKLIFE Code to predict boraflex degradation. Also, DEC plans to test for available boraflex using neutron blackness testing every 3 years. The staff indicated that the review and approval of credit for boraflex is a first-of-a kind that will require additional time than just the approval for soluble boron.

Enclosure 1 lists the meeting participants. Enclosure 2 is the handout provided by DEC.

"p~w AC Wr Frank Rinaldi, Project Manager Project Directorate ll-2 Division of Reactor Projects - 1/Il Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-70

Enclosures:

1. Meeting Attendees
2. DEC Handout cc w/encis: See next page I-l

,.. 1' l McGuire Nuclear Station

! cc:

l Ms. Lisa F. Vaughn Ms. Karen E. Long i- Legal Department (PBO5E) Assistant Attorney General

! Duke Energy Corporation North Carolina Department of I 422 South Church Street Justice Charlotte, North Carolina 28201-1006 P. O. Box 629

. Raleigh, North Carolina 27602 l County Manager of

Mecklenburg County L. A. Keller 720 East Fourth Street Manager- Nuclear Regulatory Charlotte, North Carolina 28202 Licensing Duke Energy Corporation {

MichaelT. Cash 526 South Church Street -1 Regulatory Compliance Manager Charlotte, North Carolina 28201-1006 l l: Duke Energy Corporation

. McGuire Nuclear Site .

Regional Administrator, Region il i 12700 Hagers Ferry Road U.S. Nuclear Regulatory Commission  !

Huntersville, North Carolina 28078 Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 J. Michael McGarry, lil, Esquire Atlanta, Georgia 30303 i Winston and Strawn i 1400 L Street, NW. Elaine Wathen, Lead REP Planner i

. Washington, DC 20005 Division of Emergency Management 116 West Jones Street Senior Resident inspector Raleigh, North Carolina 27603-1335  ;

c/o U.S. Nuclear Regulatory Commission .

i 12700 Hagers Ferry Road Mr. Richard M. Fry, Director  !

- Huntersville, North Carolina 28078 Division of Radiation Protection -

North Carolina Department of

- Dr. John M. Barry Environment, Health and Natural

- Mecklenberg County Resources  !

p Department of Environmental 3825 Barrett Drive Protection Raleigh, North Carolina 27609-7721 700 N. Tryon Street Charlotte, North Carolina 28202 Mr. T. Richard Puryear Owners Group (NCEMC)

Mr. Steven P. Shaver Duke Energy Corporation L Senior Sales Engineer 4800 Concord Road Westinshouse Electric Company York, South Carolina 29745

' 5929 Camogie Blvd.

Suite 500 Mr. H. B. Barron

! Charlotte, North Carolina 28209 Vice President, McGuire Site L Duke Energy Corporation i 12700 Hagers Ferry Road Huntersville, North Carolina 28078

[

i y

. l

)

1 i

' Distribution for Meetina Summary dated February 4, 1999 E-MAIL - . HARD COPY $

. S. Collins /R. Zimmerman Docket File 1 B. Boger - PUBLIC i J. Zwolinski PDil-2 Rdg. l H. Berkow F. Rinaldi 1

I.. Ber:y OGC  !

L Kopp ACRS D. Jackson K. Parczewski

. C. Lauron M. Tschiltz, EDO L Plisco, Ril C. Ogle, Ril l

J e,

.J i

1 l

I l

l

l.  :

l-i

. . l 6 .

)

i

.~

l l

l LIST OF PARTICIPANTS MEETING WITH DUKE ENERGY CORPORATION FEBRUARY 4.1998 NAME . AFFILIATION Frank Rinaldi NRC/NRR/ Project Directorate ll-2 l Mike Cash Duke Energy Corporation, Regulatory Compliance I Julius Bryant Duke Energy Corporation, Regulatory Compliance L Keith Waldrop Duke Energy Corporation, Fuel Management / Criticality Paul Guill Duke Energy Corporation, Nuclear Engineering Gary Walden Duke Energy Corporation, Nuclear Engineering l Jimmy Glenn Duke Energy Corporation, Nuclear Engineering L

. Diana Jackson NRC/NRR/ Plant Systems Branch Kris Parczewski NRC/NRR/ Materials and Chemical Engineering Branch

j. - Carolyn Lauron NRC/NRR/ Materials and Chemical Engineering Branch Larry Kopp NRC/NRR/ Reactor Systems Branch i

! 1 i

j j

l i

I '

j ,,

l-h Enclosure 1

, - , . =

,* O ,,

EdPower.

a o+r- ac .,,

. t Management of Boraflex Issues l at McGuire Nuclear Station L

XRC Meeting 4

January 27,1999 1 5:

4 Enclosure 2

s' e >

EnDuke '

C#-Power, c., Meeting Purpose a u

i
  • Review status of Boraflex degradation and ,

subsequent corrective actions; Review and discuss proposed Technical Specification and regulatory commitments. o i

li I

2 5

! l , I t :!  :  :  : .

, i -,

e a 4 n t i

n s i

o U l e

i l

o 3

t o u o t

a w Ft i P .

T t n nl u e1 S e e u00 r s u

ph F P S c a h o d e nn e r e a t o

e g t pi g l n a oS c i t

Ri dcf lo hc r e

u s ewe o a o N WP DP Et w e

r l r*

p -

e(p- e i s u

J 4

{d _/Mn wq$

g{he+;S;g$k,F y

- e.(

'+ s v.

c4 a G hd,exdj f 41 - -

h cf t

f~

.^ +,.

c i kh%n$wf i

l E @

M hJ E$m,~mT'

'sM a

~-

y.

M

$$m:~ a wn

c. $M=x: 1~

E mfr b' -

$fw?p M

w@e sn?g

.W g$',m=.

l 2$

ye,D h

y k ,t O g

h@#ps%;5qa-r s?.Ws "

f)

J s

'2 mmi 1 7

N$+,5W u t

! $&}j;pmig .

g

. .l -

EllhDuke EdPower.

MNS S E ent Fuel ~!

'*"~"

  • Pool Overview High deilsity re-rack with Boraflex design in both McGuire units;
  • Duke has monitored pools and racks to detect degradation of Boraflex;
  • There are indications of Boraflex degradation in both units' racks.

4 3

. e'

  • m ouge .

EdPower.

'~~""~"'

Industry Experience a Research started in 1987;

  • Industry User's Group formed,  ;

Enhanced measurement and computer .

model for monitoring Boraflex health developed in 1996; 5

?: .

Duke ";

  1. ffE*i., McGuire Efforts
  • Neutron " blackness" testing in 1991; Duke Power Company has provided responses to 3RC Generic Letter 96-04;
  • BADGER demonstration in January 1997;
  • Criticality analysis revised; i

A MNS-specific RACKLIFE model was developed to i

assist in assessment of pool degradation; .

Monitoring pool chemistry.

k

_ - __- --- __a

i!  ! l .! .l i,l i. + i:!

. 1(  ! ;

~

. 'o n "e

- i g

l b

a 7

s n r ed e s .

o e r i nd e pl i a meinOr- o

.. r a "t t s d ut n -

i l a s n e

- d e n d e ni a r o a c nS a p; t e

o ms n oN xd e e nt e s e ml r l i om o d CM t

l f

a r g d

a r l e o t

r s ns a

e pa h h moa t

nt a o e oi t e Bd I cb Bw r

r - , *

. u .' A  ; Y. .. x ;-

C W

?<

k

-. y.

r.

~^

- c'J ee-s, kw m.

s_

uo m DP-

- 5

.x y ad' E

'l, '

. *1 oake yff~"'*l;, MNS Options Considered

  • Poison ~ inserts; Restrictive storage patterns; Re-rack Region One;
  • Boraflex degradation chemicalinhibitors; Implement WCAP-14416 methodology.

8

_ _ _ - - _ _ _ _ _ . _ - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ - - _ _ - _ _ _ _ _ _ _ _ _ - _ _ .l

e l

. o- .  ;

e m oake =-

CdPower.

-- . a Option Chosen i

i MNS has chosen to implement WCAP- ,

14416 ~ methodology for taking credit for soluble boron in place of degrading Boraflex.

t I

i  !

c

[

9 ~

i '?

e' .

O Duke "

r# Power.

~ ~ c.,,

Tech Spec Submittal l i

Based on WCAP methodology;

  • Criticality analysis indicates current fuel inventories cannot be accommodated using WCAP methodology alone; WCAP methodology does not consider

,- degrading poison material;

  • MXS seeking partial credit for Boraflex.

~

10

r# Power.

anwcm Pronosed Y TS Submittal Defines two sub-regions in Region 1:

- Region 1A (partial Boraflex)

- Region IB (no Boraflex)

Defines two sub-regions in Region 2:

- Region 2A (partial Boraflex)

- Region 2B (no Boraflex) -

3 storage patterns in each region:

- Unrestricted

- Restricted w/ Filler

- Checkerboard w/ empty cells New SLC for poison materiallimit; Propose defming sub-regions in Bases.

11

. . . _ _ . . . . . . ___ .m____._ _ _ . . _ . . _ . _ . . _ _ _ _ . . . . _ _ _ _ _ _ _ _ . . - . _ _ _ _ _ . _ . _ . . _ _ _

i DRAFT SLC Spent Fuel Pool Storage Rack Poison Material -

2 LCO The storage rack poison material Boron 10 areal density shall be greater than or equalto:

0.005 gm Bidem' for Region 1 A i 0 gm Bidem' for Region 1B i 0.003 gm Bidem' for Region 2A i

0 gm Bidem' for Region 2B APPLICABILITY: When a fuel assembly is stored in a spent fuel rack cell, location.

ACTIONS 1

CONDITION REQUIRED ACTION COMPLETION TIME i

NOTE LCO 3.0.3 ls not applicable.

A. Spent fuelpool storage rack A.1 Perform SR 3.7.14.1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> poison materialnot within M

- limit.= Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until affected fuel assembly moved li M

! A.2 Verifyfuelassemblyin affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

  • location meets 3.7.15(b) for Region 1 or 3.7.15(d) for Region 2

) B. Required Action and . B.1 initiate action to move affected immediately L associated Completion Time fuel assemblyto acceptable j of Condition A not met. location i-i . l r;

. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR Verify the spent fuel pool storage rack poison material is within 3 years limits.

e . r. .  ::- ' -. ,.

.a. = = = = - - - - -

l . .

i Duke "

, Pow- c ms-xx .,, Conclusions g l .,

1 ll l i Tech Spec Submittal by 2/28/1999; l Current Operability expires 12/31/1999; g l XRC approval needed by 12/31/1999; l Dry Storage to begin in 2000 to provide

! additional storage capacity;

! Other options are still under consideration i

for long term resolution.

j 13

A--446.-oaso A - =-& - .t.6,a4. MAzoee k & ,4 -4hAA48 4 -U-n A6 -~.bd- d--A+.3iR43 3- 4,s bes-W.,Aere "n

- e.swMe swn--e,._s-,-m-~Aamoswsn a os%misaAe-ms.u-masu.-an,ema-- mmsaw a O

e e

e e;

1 i

i I

e M i CD j oo e-+

M*

M

-~- - - -.. .-. . .-.....:. ..- _..-.. = = r.. =-.= .

- ~ ~ - , - - - ,-. --