ML19325C897: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 21: | Line 21: | ||
g 1 ._.t. * | g 1 ._.t. * | ||
~ }<i Q 4 : | ~ }<i Q 4 : | ||
e y39 .. . _ | e y39 .. . _ | ||
p ic ;./ N Commonweehh Edison . | p ic ;./ N Commonweehh Edison . | ||
y , gar g ;b l,- ' i _ d 72 West Adams Street Chicago, Illinois b,' jy' \ '''' / Address Reply to: Pc.t Offica Box 767 --- | y , gar g ;b l,- ' i _ d 72 West Adams Street Chicago, Illinois b,' jy' \ '''' / Address Reply to: Pc.t Offica Box 767 --- | ||
4, , A4 Chicago, Illinois 60690 0767 jy Qi ,' < | 4, , A4 Chicago, Illinois 60690 0767 jy Qi ,' < | ||
c_ , | c_ , | ||
t .- | t .- | ||
p,g : October 11, 1989: | p,g : October 11, 1989: | ||
y , 1 | y , 1 | ||
:[ Dr; Thomas E..Murley. Director? | :[ Dr; Thomas E..Murley. Director? | ||
' Office of Nuclear Reactor Regulation 4 | ' Office of Nuclear Reactor Regulation 4 U.SL Nuclear Regulatory Commission -l 4 ' | ||
U.SL Nuclear Regulatory Commission -l | |||
Hashington, DC 20555 , | Hashington, DC 20555 , | ||
^ | ^ | ||
==Subject:== | ==Subject:== | ||
Quad Cities Nuclear Power Station Unitel l Cycle 11 Reload | Quad Cities Nuclear Power Station Unitel l Cycle 11 Reload | ||
,o JiRC Docket No. 50-254 ; | ,o JiRC Docket No. 50-254 ; | ||
~ | ~ | ||
==Reference:== | ==Reference:== | ||
| Line 55: | Line 43: | ||
m - to Remove Cycle-Specific Core Limits from the-. . | m - to Remove Cycle-Specific Core Limits from the-. . | ||
- Technical Specification", dated July' 11,:1989/ , | - Technical Specification", dated July' 11,:1989/ , | ||
.n , ; | .n , ; | ||
tv s A , | tv s A , | ||
.Dr. Murley:' | .Dr. Murley:' | ||
\r | \r | ||
| Line 65: | Line 51: | ||
1 . | 1 . | ||
E[] - - - | E[] - - - | ||
' Quad Cities Station Unit 1,:which has completed its tenth cycle of u | ' Quad Cities Station Unit 1,:which has completed its tenth cycle of u | ||
~ | ~ | ||
L, operation,=is currently preparing for. Cycle-11 startup. The purpose of this 3 | L, operation,=is currently preparing for. Cycle-11 startup. The purpose of this 3 | ||
. letter is twofold: .'(1) -to advise you of: Commonwealth, Edison's review and ; | . letter is twofold: .'(1) -to advise you of: Commonwealth, Edison's review and ; | ||
$< - approval..'of the Cycle 11-reload!under the provisions of 10 CFR 50.59,-and (2) . , | $< - approval..'of the Cycle 11-reload!under the provisions of 10 CFR 50.59,-and (2) . , | ||
| Line 78: | Line 60: | ||
- cycle 7as required by Generic-Letter 88-16. Note that Edison has submitted the- | - cycle 7as required by Generic-Letter 88-16. Note that Edison has submitted the- | ||
- necess'ary Technical Specification changes-(See Reference) to incorporate:the . | - necess'ary Technical Specification changes-(See Reference) to incorporate:the . | ||
/ , - COLR. . Edison's.10 CFR 50.59 evaluation assumes approval of-this-amendment - | / , - COLR. . Edison's.10 CFR 50.59 evaluation assumes approval of-this-amendment - | ||
< prior to unit startup. | < prior to unit startup. | ||
* y s | * y s | ||
- The Quad Cities Unit 1 Cycle 11 core consists of NRC approved fuel designs:and was designed to' operate under currently approved fuel design ! | |||
- The Quad Cities Unit 1 Cycle 11 core consists of NRC approved fuel | |||
designs:and was designed to' operate under currently approved fuel design ! | |||
q parameters, Technical Specifications and related bases such that: { | q parameters, Technical Specifications and related bases such that: { | ||
W ' | W ' | ||
' 1 )- . Core operating characteristics will be less limiting than those previously reviewed and accepted; or | ' 1 )- . Core operating characteristics will be less limiting than those previously reviewed and accepted; or ll-} | ||
ll-} | |||
: 2) For those' postulated incidents analyzed and reported in the Final Safety Analysis ~ Report (FSAR) which could potentially be affected by the fuel reload,: re-analysis using NRC-approved methods has demonstrated that the results of the postulated events are within allowable limits. | : 2) For those' postulated incidents analyzed and reported in the Final Safety Analysis ~ Report (FSAR) which could potentially be affected by the fuel reload,: re-analysis using NRC-approved methods has demonstrated that the results of the postulated events are within allowable limits. | ||
Off 1 , | Off 1 , | ||
0318T:1 891018o056 891011 i PDR ADOCK 0500o254 p | 0318T:1 891018o056 891011 i PDR ADOCK 0500o254 p | ||
m- PDC | m- PDC | ||
: 5. k- - 3 | : 5. k- - 3 | ||
* ", [ . | * ", [ . | ||
.c. 3, i | .c. 3, i | ||
b . | b . | ||
Dr. T.E. Nurley October 11, 1989 | Dr. T.E. Nurley October 11, 1989 Commonwealth Edison has performed a detailed review of the relevant . | ||
Commonwealth Edison has performed a detailed review of the relevant . | |||
licensing documents, the bases, and references. Based on the review..a safety j evaluation was prepared as required by 10 CFR 50.5?(a,b) and submitted to ' | licensing documents, the bases, and references. Based on the review..a safety j evaluation was prepared as required by 10 CFR 50.5?(a,b) and submitted to ' | ||
On-Site and Off-Site Review. As in the past, the. reload licensing documents j | On-Site and Off-Site Review. As in the past, the. reload licensing documents j | ||
.were prepared using previously approved methodologies as reported in the FSAR ; | .were prepared using previously approved methodologies as reported in the FSAR ; | ||
NEDE-24011 (GESTAR), and other generically approved documents. i l | NEDE-24011 (GESTAR), and other generically approved documents. i l | ||
.: Edison has reviewed the cycle-specific licensing results and concluded j that additional Technical-Specification changes are not required for Cycle 11- ' | .: Edison has reviewed the cycle-specific licensing results and concluded j that additional Technical-Specification changes are not required for Cycle 11- ' | ||
operation at Quad Cities Unit 1 assuming the reference amendment receives NRC approval. Furthermore, Edison has completed On-Site and Off-Site Reviews-which determined that no unreviewed safety questions are created by the reload. .) | operation at Quad Cities Unit 1 assuming the reference amendment receives NRC approval. Furthermore, Edison has completed On-Site and Off-Site Reviews-which determined that no unreviewed safety questions are created by the reload. .) | ||
1 \ | 1 \ | ||
'Therefore, application for an amendment to the Quad Cities Unit 1 | 'Therefore, application for an amendment to the Quad Cities Unit 1 1 | ||
operating license is not required for resumption of operation with the Cycle 11 reload core. The estimated startup is November 20, 1989. 1 l | |||
L | L | ||
'If-there are any further questions regarding this matter, please j i | 'If-there are any further questions regarding this matter, please j i | ||
| Line 128: | Line 91: | ||
Very truly yours, l | Very truly yours, l | ||
g - | g - | ||
J. A. S11ady Nuclear Licensing Administrator | J. A. S11ady Nuclear Licensing Administrator im Attachment. | ||
.cc: T.M. Ross - Project. Manager, NRR R.L. Higgins - Senior Resident Inspector, Quad Cities 0318T:2 | |||
.cc: T.M. Ross - Project. Manager, NRR R.L. Higgins - Senior Resident Inspector, Quad Cities | |||
0318T:2 | |||
_ - - - _ _ - _ - _ _ _ _ _ _ _ _}} | _ - - - _ _ - _ - _ _ _ _ _ _ _ _}} | ||
Revision as of 00:48, 1 February 2020
| ML19325C897 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities |
| Issue date: | 10/11/1989 |
| From: | Silady J COMMONWEALTH EDISON CO. |
| To: | Murely T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19325C898 | List: |
| References | |
| 0318T:1, 318T:1, GL-88-16, NUDOCS 8910180056 | |
| Download: ML19325C897 (2) | |
Text
m;; -
'E #
g 1 ._.t. *
~ }<i Q 4 :
e y39 .. . _
p ic ;./ N Commonweehh Edison .
y , gar g ;b l,- ' i _ d 72 West Adams Street Chicago, Illinois b,' jy' \ ' / Address Reply to: Pc.t Offica Box 767 ---
4, , A4 Chicago, Illinois 60690 0767 jy Qi ,' <
c_ ,
t .-
p,g : October 11, 1989:
y , 1
- [ Dr; Thomas E..Murley. Director?
' Office of Nuclear Reactor Regulation 4 U.SL Nuclear Regulatory Commission -l 4 '
Hashington, DC 20555 ,
^
Subject:
Quad Cities Nuclear Power Station Unitel l Cycle 11 Reload
,o JiRC Docket No. 50-254 ;
~
Reference:
J. A.;Silady to T.E. Murley, " Quad Cities Nuclear- .t Power Station Units 1:and 2, Proposed Amendment "
m - to Remove Cycle-Specific Core Limits from the-. .
- Technical Specification", dated July' 11,:1989/ ,
.n , ;
tv s A ,
.Dr. Murley:'
\r
=
g- ,
1 .
E[] - - -
' Quad Cities Station Unit 1,:which has completed its tenth cycle of u
~
L, operation,=is currently preparing for. Cycle-11 startup. The purpose of this 3
. letter is twofold: .'(1) -to advise you of: Commonwealth, Edison's review and ;
$< - approval..'of the Cycle 11-reload!under the provisions of 10 CFR 50.59,-and (2) . ,
C to transmit the attached Core Operating Limits Report (COLR) forLthe upcoming .
~ l
- cycle 7as required by Generic-Letter 88-16. Note that Edison has submitted the-
- necess'ary Technical Specification changes-(See Reference) to incorporate:the .
/ , - COLR. . Edison's.10 CFR 50.59 evaluation assumes approval of-this-amendment -
< prior to unit startup.
- y s
- The Quad Cities Unit 1 Cycle 11 core consists of NRC approved fuel designs:and was designed to' operate under currently approved fuel design !
q parameters, Technical Specifications and related bases such that: {
W '
' 1 )- . Core operating characteristics will be less limiting than those previously reviewed and accepted; or ll-}
- 2) For those' postulated incidents analyzed and reported in the Final Safety Analysis ~ Report (FSAR) which could potentially be affected by the fuel reload,: re-analysis using NRC-approved methods has demonstrated that the results of the postulated events are within allowable limits.
Off 1 ,
0318T:1 891018o056 891011 i PDR ADOCK 0500o254 p
m- PDC
- 5. k- - 3
- ", [ .
.c. 3, i
b .
Dr. T.E. Nurley October 11, 1989 Commonwealth Edison has performed a detailed review of the relevant .
licensing documents, the bases, and references. Based on the review..a safety j evaluation was prepared as required by 10 CFR 50.5?(a,b) and submitted to '
On-Site and Off-Site Review. As in the past, the. reload licensing documents j
.were prepared using previously approved methodologies as reported in the FSAR ;
NEDE-24011 (GESTAR), and other generically approved documents. i l
.: Edison has reviewed the cycle-specific licensing results and concluded j that additional Technical-Specification changes are not required for Cycle 11- '
operation at Quad Cities Unit 1 assuming the reference amendment receives NRC approval. Furthermore, Edison has completed On-Site and Off-Site Reviews-which determined that no unreviewed safety questions are created by the reload. .)
1 \
'Therefore, application for an amendment to the Quad Cities Unit 1 1
operating license is not required for resumption of operation with the Cycle 11 reload core. The estimated startup is November 20, 1989. 1 l
L
'If-there are any further questions regarding this matter, please j i
contact this office. l I
Very truly yours, l
g -
J. A. S11ady Nuclear Licensing Administrator im Attachment.
.cc: T.M. Ross - Project. Manager, NRR R.L. Higgins - Senior Resident Inspector, Quad Cities 0318T:2
_ - - - _ _ - _ - _ _ _ _ _ _ _ _