ML20129D077: Difference between revisions

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UNITED STATES NUCLEAR REGULATORY COMMISSION j
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;                  k.            #                                      October 18, 1996                                     JMilhoan
October 18, 1996 JMilhoan HThompson cmN ra lia, NRR i
;                        ..,,,                                                                                                HThompson cmN ra lia, NRR i                                                                                                                               DDorman, NRR j                                                                                                                               KCyr, 0GC HMiller, RI l
DDorman, NRR j
i                          Mr. Henry Myers                                                                                     GT96627
KCyr, 0GC HMiller, RI i
:                          P. O. Box 88                                                                                         ED0 r/f
Mr. Henry Myers GT96627 l
;.                        Peaks Island, Maine 04108 i                        
P. O. Box 88 ED0 r/f Peaks Island, Maine 04108 i


==Dear Mr. Myers:==
==Dear Mr. Myers:==
 
i I am responding to your letters of August 10 and August 14, 1996, in which you j
i                         I am responding to your letters of August 10 and August 14, 1996, in which you j '
questioned the regulatory. basis for the January 3, 1996 NRC Order to Maine Yankee permitting operation of the plant at 90% power.
questioned the regulatory. basis for the January 3, 1996 NRC Order to Maine Yankee permitting operation of the plant at 90% power. The Commission recognizes that you and other citizens of Maine are concerned about interim j                         operation of the plant pending the completion 'of licensee actions that would i                         bring the plant into conformance with regulatory guidance relevant to j                         applicable NRC regulations for operation above 2440 MWt. However, before issuing the Order, the Director of NRC's Office of Nuclear Reactor Regulation
The Commission recognizes that you and other citizens of Maine are concerned about interim j
;                          (NRR) explained to me the basis for the proposed action. I was satisfied that j                         the proposed action was sound and that it provided the necessary assurance that operation of Maine Yankee at the reduced power level was consistent with public health and safety. The Commission supports the action of the Director i                         of NRR in issuing the Order in accordance with his general delegated authority
operation of the plant pending the completion 'of licensee actions that would i
:                          to issue orders to power reactor licensees in order to protect public health i                         and safety under the provisions of 10 CFR Parts 2 and 50, including the l                         authority specified in 10 CFR 50.46(a)(2). There has been no information that j                         would cause the Commission to reconsider that action.
bring the plant into conformance with regulatory guidance relevant to j
j                         As you know, the NRC staff received allegations in December 1995 regarding the                                           ,
applicable NRC regulations for operation above 2440 MWt.
!                          inadequacy of the small-break loss-of-coolant accident (SBLOCA) analysis and                                             I i                         containment analysis for Maine Yankee. The Director of the Office of Nuclear                                             !
However, before issuing the Order, the Director of NRC's Office of Nuclear Reactor Regulation (NRR) explained to me the basis for the proposed action.
!                          Reactor Regulation issued the " Confirmatory Order Suspending Authority for and                                           i
I was satisfied that j
the proposed action was sound and that it provided the necessary assurance that operation of Maine Yankee at the reduced power level was consistent with public health and safety.
The Commission supports the action of the Director i
of NRR in issuing the Order in accordance with his general delegated authority to issue orders to power reactor licensees in order to protect public health i
and safety under the provisions of 10 CFR Parts 2 and 50, including the l
authority specified in 10 CFR 50.46(a)(2).
There has been no information that j
would cause the Commission to reconsider that action.
j As you know, the NRC staff received allegations in December 1995 regarding the inadequacy of the small-break loss-of-coolant accident (SBLOCA) analysis and i
containment analysis for Maine Yankee. The Director of the Office of Nuclear Reactor Regulation issued the " Confirmatory Order Suspending Authority for and
{
{
Limfting Power Operation and Containment Pressure (Effective Immediately) and
Limfting Power Operation and Containment Pressure (Effective Immediately) and Demand for Information" (Order) on January 3, 1996, on the basis of technical l
!                          Demand for Information" (Order) on January 3, 1996, on the basis of technical l                         information collected during the NRC staff's. evaluation of the allegations.
information collected during the NRC staff's. evaluation of the allegations.
:                          The Order was issued for the explicit purpose of ensuring safe operation of Maine Yankee pending completion of the staff's evaluation of the Maine Yankee i                         emergency core cooling systems and containment design. The Order recited as a
The Order was issued for the explicit purpose of ensuring safe operation of Maine Yankee pending completion of the staff's evaluation of the Maine Yankee i
!                          basis for those restrictions that the Maine Yankee Atomic Power Company (the i                         licensee) had not. applied computer code RELAP5YA, as it had proposed for. Cycle
emergency core cooling systems and containment design. The Order recited as a basis for those restrictions that the Maine Yankee Atomic Power Company (the i
;                          15 SBLOCA analyses, in conformance with the requirements of 10 CFR 50.46, and j                         did not satisfy TMI Action P1an Items II.K.3.30 and II.K.3.31. As explained i                         in letters to you dated June 18, July 9, and August 9,1996, the Order did not
licensee) had not. applied computer code RELAP5YA, as it had proposed for. Cycle 15 SBLOCA analyses, in conformance with the requirements of 10 CFR 50.46, and j
                          " waive" TMI Action ' Plan Items II.K.3.30 and II.K.3.31. To the contrary, the i
did not satisfy TMI Action P1an Items II.K.3.30 and II.K.3.31. As explained i
j                        Order required the submission of a SBLOCA analysis that, if submitted and
in letters to you dated June 18, July 9, and August 9,1996, the Order did not i
!                        accepted, would bring the licensee into conformance with the regulatory
" waive" TMI Action ' Plan Items II.K.3.30 and II.K.3.31.
;                          guidance of TMI Action Plan Items-.II.K.3.30 and II.K.3.31 and into compliance                                         j j                         -with the requirements of 10 CFR 50.46(a)(1) for operation above 2440 MWt.
To the contrary, the j
9610240192 961018                                                                                                     I
Order required the submission of a SBLOCA analysis that, if submitted and accepted, would bring the licensee into conformance with the regulatory guidance of TMI Action Plan Items-.II.K.3.30 and II.K.3.31 and into compliance j
-                    PDR     COMMS NRCC CORRESPONDENCE PDR                     .
j
                        '[0riginated By:
-with the requirements of 10 CFR 50.46(a)(1) for operation above 2440 MWt.
RC D. Dorman NRR]                                                             E CENTER COPY
9610240192 961018 I
PDR COMMS NRCC CORRESPONDENCE PDR RC E CENTER COPY
'[0riginated By:
D. Dorman NRR]


c e, .
c e,
2 Additionally, as explained in letters to you dated June 18, and July 9, 1996, the specific regulation that authorizes the restrictions imposed on the operation of Maine Yankee by the Order is 10 CFR 50.46(a)(2). Although not specifically referenced by the Order, that specific authority is included within the Commission's general authority cited in the Order, which was explicitly issued under the authority of Sections 103, 161b, 1611, 1610, 182, and 186 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.202 and 10 CFR Part 50. (See Order, Section VII.)   In your letter of August 14, 1996, you state that you "do not dispute that 10 CFR 50.46(a)(2) authorizes the NRC to impose the limitation on the power level at which Maine Yankee operates."
2 Additionally, as explained in letters to you dated June 18, and July 9, 1996, the specific regulation that authorizes the restrictions imposed on the operation of Maine Yankee by the Order is 10 CFR 50.46(a)(2). Although not specifically referenced by the Order, that specific authority is included within the Commission's general authority cited in the Order, which was explicitly issued under the authority of Sections 103, 161b, 1611, 1610, 182, and 186 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.202 and 10 CFR Part 50.
With respect to your questioning the authority of the Commission to permit operation of Maine Yankee at all, the choice of an appropriate mechanism for correcting an apparent violation rests within the sound discretion of the agency, and the paramount concern in exercising that discretion is public health and safety (Petition for Emergency and Remedial Action, CLI-78-6, 7 NRC 400, 405-406 (1978); See also Advanced Medical Systems, Inc. , CLI-94-6, 39 NRC 285, 312-313 (1994)). The staff was satisfied that Maine Yankee would be operated safely at the reduced power level, in accordance with 50.46(a)(2),
(See Order, Section VII.)
but did not perform an independent SBLOCA analysis because it was determined to be unnecessary with the restrictions to be imposed. Specifically, with the imposed power penalty, the licensee's approved large-break loss-of-coolant accident analysis bounded credible design-basis accidents. The Order contains an extensive discussion of the safety basis for the staff's conclusion that power operation with the imposed restrictions did not pose an undue risk to public health and safety.
In your letter of August 14, 1996, you state that you "do not dispute that 10 CFR 50.46(a)(2) authorizes the NRC to impose the limitation on the power level at which Maine Yankee operates."
With respect to your questioning the authority of the Commission to permit operation of Maine Yankee at all, the choice of an appropriate mechanism for correcting an apparent violation rests within the sound discretion of the agency, and the paramount concern in exercising that discretion is public health and safety (Petition for Emergency and Remedial Action, CLI-78-6, 7 NRC 400, 405-406 (1978); See also Advanced Medical Systems, Inc., CLI-94-6, 39 NRC 285, 312-313 (1994)).
The staff was satisfied that Maine Yankee would be operated safely at the reduced power level, in accordance with 50.46(a)(2),
but did not perform an independent SBLOCA analysis because it was determined to be unnecessary with the restrictions to be imposed.
Specifically, with the imposed power penalty, the licensee's approved large-break loss-of-coolant accident analysis bounded credible design-basis accidents.
The Order contains an extensive discussion of the safety basis for the staff's conclusion that power operation with the imposed restrictions did not pose an undue risk to public health and safety.
Regarding your question as to the view of the Office of the General Counsel (0GC), you should be aware that 0GC provided advice and counsel to the staff of the Office of Nuclear Reactor Regulation (NRR) during the development of the Order and that, in 0GC's view, the Order is legally sufficient. Allowing Maine Yankee operation up to 90%, notwithstanding nonconformance with TMI items II.K.3.30 and II.K.3.31, was considered during the development of the Order.
Regarding your question as to the view of the Office of the General Counsel (0GC), you should be aware that 0GC provided advice and counsel to the staff of the Office of Nuclear Reactor Regulation (NRR) during the development of the Order and that, in 0GC's view, the Order is legally sufficient. Allowing Maine Yankee operation up to 90%, notwithstanding nonconformance with TMI items II.K.3.30 and II.K.3.31, was considered during the development of the Order.
I hope this information will help resolve your concerns about interim operation of Maine Yankee.
I hope this information will help resolve your concerns about interim operation of Maine Yankee.
Sincerely,                               I l
Sincerely, k
k Shirley Ann Jackson                     ;
Shirley Ann Jackson cc:
cc: Senator Cohen Senator Snowe Senator Lieberman Senator Biden Representative Dingell Representative Markey I
Senator Cohen Senator Snowe Senator Lieberman Senator Biden Representative Dingell Representative Markey I


y g
y g
* Mr. Henry R. Myers                                         Regarding your statements as to informing the public of the governing regulations and the necessity of a small-break loss-of-coolant analysis to be performed in this matter, I would agree that the staff could have been more clear as to the specific regulations in question. Nevertheless, it is clear that 10 CFR 50.46(a)(2) provides the Director of the Office of Nuclear Reactor Regulation with the authority to impose restrictions on reactor operations to ensure that the criteria of 10 CFR 50.46(a)(1) are met. I do note that the staff's analysis and technical basis are comprehensive and support the order.
Mr. Henry R. Myers Regarding your statements as to informing the public of the governing regulations and the necessity of a small-break loss-of-coolant analysis to be performed in this matter, I would agree that the staff could have been more clear as to the specific regulations in question. Nevertheless, it is clear that 10 CFR 50.46(a)(2) provides the Director of the Office of Nuclear Reactor Regulation with the authority to impose restrictions on reactor operations to ensure that the criteria of 10 CFR 50.46(a)(1) are met.
I do note that the staff's analysis and technical basis are comprehensive and support the order.
I trust you will appreciate that the Commission has followed this matter closely and would not hesitate to intervene should any improprieties arise.
I trust you will appreciate that the Commission has followed this matter closely and would not hesitate to intervene should any improprieties arise.
Thank you for your expressions of concern and I trust you find my views responsive to your concerns.
Thank you for your expressions of concern and I trust you find my views responsive to your concerns.
Sincerely, (Original Signed By)                                                   l l
Sincerely, (Original Signed By)
Shirley Ann Jackson                                                     '
Shirley Ann Jackson I
I cc:
cc:
Senator Cohen Senator Snowe Senator Lieberman Senator Biden Congressman Dingell Congressman Markey DISTRIBUTION:
Senator Cohen Senator Snowe Senator Lieberman Senator Biden Congressman Dingell Congressman Markey DISTRIBUTION:
DOCKET (w/ orig incoming)             WRussell/FMiraglia                   PDI-3 Reading
DOCKET (w/ orig incoming)
)     PUBLIC (w/ incoming)                   RZimmerman                           NRR Mailroom (w/incom)
WRussell/FMiraglia PDI-3 Reading
ED0 # GT96627                         AThadani                             SECY CRC 96-0885 & 0887 EDO Reading File                       TMartin                               HMiller, R-I JTaylor                               SVarga                               JRogge, R-I JMilhoan                               JZwolinski                           JGoldberg, 0GC HThompson                             ETrottier                             0CA JBlaha                                 PMilano                               OPA KCyr, 0GC                             DDorman DOCUMENT NAME: G:\00RMAN\GT96627.GRN                               *See previous concurrence                             ,
)
To receive a copy of this doctament, indicate in the box: "c" = Copy without attachment / enclosure   "E" =             '
PUBLIC (w/ incoming)
Copy with attachnent/ enclosure   "N" = No copy OFFICE PM:DRPE lE     LA:DRPE   lE    Tech Ed l E     DD:DRPE   lN    D:DRPE   l       D:DSSA       lN MAME   DDorman*       EPeyton           BCalure         JZwolinski*       SVarga*         GHolahan*
RZimmerman NRR Mailroom (w/incom)
DATE   08/22/ % t    09/ /%           09/ /%         08/22/96         08/22/ %         09/03/96 OFFICE ADP@ l" TL     OGC       lN    D:NRR     l     EDO       l     OCM         l                 l NAME   RZimmer 4 V     JGolderg       WRussell       JTaylor           SJackson                         _
ED0 # GT96627 AThadani SECY CRC 96-0885 & 0887 EDO Reading File TMartin HMiller, R-I JTaylor SVarga JRogge, R-I JMilhoan JZwolinski JGoldberg, 0GC HThompson ETrottier 0CA JBlaha PMilano OPA KCyr, 0GC DDorman DOCUMENT NAME: G:\\00RMAN\\GT96627.GRN
                                                                                                                                )
*See previous concurrence To receive a copy of this doctament, indicate in the box:
DATE     09/ J /% f       09/ /%           09/ /%         09/ /%             09/ /96                                       1 7                       0FFICIAL RECORD COPY                                                             i
"c" = Copy without attachment / enclosure "E" =
Copy with attachnent/ enclosure "N" = No copy OFFICE PM:DRPE lE LA:DRPE l E Tech Ed l E DD:DRPE l N D:DRPE l
D:DSSA lN MAME DDorman*
EPeyton BCalure JZwolinski*
SVarga*
GHolahan*
DATE 08/22/ %
09/ /%
09/ /%
08/22/96 08/22/ %
09/03/96 t
OFFICE ADP@ l" TL OGC l N D:NRR l
EDO l
OCM l
l NAME RZimmer 4 V JGolderg WRussell JTaylor SJackson DATE 09/ J /% f 09/ /%
09/ /%
09/ /%
09/ /96
)
1 7
0FFICIAL RECORD COPY i


  .    ,          ,.                \
\\
i
i t
* t ACTlDif EDO Principal Correspondence Control jFROM:.                             DUE: 08/29/96                     EDO CONTROL: GT96627 j
ACTlDif EDO Principal Correspondence Control jFROM:.
DOC DT: 08/10/96
DUE: 08/29/96 EDO CONTROL: GT96627 DOC DT: 08/10/96 j
;Hanry Myers                                                             FINAL REPLY:& 8/14/96
;Hanry Myers FINAL REPLY:& 8/14/96
'TO:
'TO:
Chairman Jackson FOR SIGNATURE OF :                             ** PRI **
Chairman Jackson FOR SIGNATURE OF :
CRC NO: 96-0887 Chairman Jackson DESC:
** PRI CRC NO: 96-0887 Chairman Jackson DESC:
ROUTING:
ROUTING:
MAINE YANKEE                                                                     Taylor Milhoan Thompson Blaha Cyr, OGC HMiller, RI DATE: 08/16/96 ASSIGNED TO:                       CONTACT:
MAINE YANKEE Taylor Milhoan Thompson Blaha Cyr, OGC HMiller, RI DATE: 08/16/96 ASSIGNED TO:
I
CONTACT:
_ _ _ _ _ . _.~ Rus s ell ~~            (y,\00RMAb"D                    ~        ' ~ ~
I (y,\\00RMAb"D
~
~ ~
_ _ _ _ _. _.~ Rus s ell ~~
SPECIAL INSTRUCTIONS OR REMARKS:
SPECIAL INSTRUCTIONS OR REMARKS:
Raf. GT96559.
Raf. GT96559.
Coordinate with OGC.
Coordinate with OGC.
NRR RECEIVED:               AUGUST 16, 1996                                                       __
NRR RECEIVED:
NRR ACTION:                 DRPE:VARGA c
AUGUST 16, 1996 NRR ACTION:
ACTION NRR ROUTING:                 RUSSELL'                                                 ~
DRPE:VARGA ACTION c
N"^$!^                       DUE To ti           DIRECTOR'S OFFIC ZIMMERMAN GRIMES                                                         /
NRR ROUTING:
B0HRER                         g                           .
RUSSELL'
                                                                                                                  ~~~~ a
~
                                                              \
N"^$!^
DUE To ti DIRECTOR'S OFFIC ZIMMERMAN GRIMES
/
B0HRER g
~~~~ a
\\
l
l


e
e OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET PAPER NUMBER:
    ,                                OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET PAPER NUMBER:     CRC-96-0887                     LOGGING DATE: Aug 16 96 ACTION OFFICE:   EDO/OGC AUTHOR:           HENRY MEYERS AFFILIATION:     MAINE ADDRESSEE:       CHAIRMAN JACKSON l
CRC-96-0887 LOGGING DATE: Aug 16 96 ACTION OFFICE:
LETTER DATE:     Aug 10 96           FILE CODE: IDR-5 MAINE YANKEE             l
EDO/OGC AUTHOR:
HENRY MEYERS AFFILIATION:
MAINE ADDRESSEE:
CHAIRMAN JACKSON LETTER DATE:
Aug 10 96 FILE CODE: IDR-5 MAINE YANKEE


==SUBJECT:==
==SUBJECT:==
MAINE YANKEE                                                 l l
MAINE YANKEE ACTION:
ACTION:           Signature of Chairman DISTRIBUTION:     CHAIRMAN, COMRS, RF SPECIAL HANDLING: SECY TO ACK CONSTITUENT:
Signature of Chairman DISTRIBUTION:
NOTES:           OCM #4906 DATE DUE:         Aug 30 96 SIGNATURE:         .                              DATE SIGNED:
CHAIRMAN, COMRS, RF SPECIAL HANDLING: SECY TO ACK CONSTITUENT:
NOTES:
OCM #4906 DATE DUE:
Aug 30 96 SIGNATURE:
DATE SIGNED:
AFFILIATION:
AFFILIATION:
l l
l l
l l
l l
EDO
EDO
                                                                            . GT96627
. GT96627
                                                      - _  -  - - - _ _              -.}}
-.}}

Latest revision as of 11:50, 12 December 2024

Responds to 960810 & 14 Ltrs Re Questions Re Regulatory Basis for 960103 NRC Order to Maine Yankee Permitting Operation of Plant at 90% Power.Order Legally Sufficient
ML20129D077
Person / Time
Site: Maine Yankee
Issue date: 10/18/1996
From: Shirley Ann Jackson, The Chairman
NRC COMMISSION (OCM)
To: Myers H
AFFILIATION NOT ASSIGNED
Shared Package
ML20129D083 List:
References
NUDOCS 9610240192
Download: ML20129D077 (5)


Text

-. -. - - -. -.

5D004 l

-[

UNITED STATES j

?'.

NUCLEAR REGULATORY COMMISSION i

j-3e 5

0 WASHINGTON. D.C. 20555-0001 Distribution:

J E

i!

JTaylor

~

k.

October 18, 1996 JMilhoan HThompson cmN ra lia, NRR i

DDorman, NRR j

KCyr, 0GC HMiller, RI i

Mr. Henry Myers GT96627 l

P. O. Box 88 ED0 r/f Peaks Island, Maine 04108 i

Dear Mr. Myers:

i I am responding to your letters of August 10 and August 14, 1996, in which you j

questioned the regulatory. basis for the January 3, 1996 NRC Order to Maine Yankee permitting operation of the plant at 90% power.

The Commission recognizes that you and other citizens of Maine are concerned about interim j

operation of the plant pending the completion 'of licensee actions that would i

bring the plant into conformance with regulatory guidance relevant to j

applicable NRC regulations for operation above 2440 MWt.

However, before issuing the Order, the Director of NRC's Office of Nuclear Reactor Regulation (NRR) explained to me the basis for the proposed action.

I was satisfied that j

the proposed action was sound and that it provided the necessary assurance that operation of Maine Yankee at the reduced power level was consistent with public health and safety.

The Commission supports the action of the Director i

of NRR in issuing the Order in accordance with his general delegated authority to issue orders to power reactor licensees in order to protect public health i

and safety under the provisions of 10 CFR Parts 2 and 50, including the l

authority specified in 10 CFR 50.46(a)(2).

There has been no information that j

would cause the Commission to reconsider that action.

j As you know, the NRC staff received allegations in December 1995 regarding the inadequacy of the small-break loss-of-coolant accident (SBLOCA) analysis and i

containment analysis for Maine Yankee. The Director of the Office of Nuclear Reactor Regulation issued the " Confirmatory Order Suspending Authority for and

{

Limfting Power Operation and Containment Pressure (Effective Immediately) and Demand for Information" (Order) on January 3, 1996, on the basis of technical l

information collected during the NRC staff's. evaluation of the allegations.

The Order was issued for the explicit purpose of ensuring safe operation of Maine Yankee pending completion of the staff's evaluation of the Maine Yankee i

emergency core cooling systems and containment design. The Order recited as a basis for those restrictions that the Maine Yankee Atomic Power Company (the i

licensee) had not. applied computer code RELAP5YA, as it had proposed for. Cycle 15 SBLOCA analyses, in conformance with the requirements of 10 CFR 50.46, and j

did not satisfy TMI Action P1an Items II.K.3.30 and II.K.3.31. As explained i

in letters to you dated June 18, July 9, and August 9,1996, the Order did not i

" waive" TMI Action ' Plan Items II.K.3.30 and II.K.3.31.

To the contrary, the j

Order required the submission of a SBLOCA analysis that, if submitted and accepted, would bring the licensee into conformance with the regulatory guidance of TMI Action Plan Items-.II.K.3.30 and II.K.3.31 and into compliance j

j

-with the requirements of 10 CFR 50.46(a)(1) for operation above 2440 MWt.

9610240192 961018 I

PDR COMMS NRCC CORRESPONDENCE PDR RC E CENTER COPY

'[0riginated By:

D. Dorman NRR]

c e,

2 Additionally, as explained in letters to you dated June 18, and July 9, 1996, the specific regulation that authorizes the restrictions imposed on the operation of Maine Yankee by the Order is 10 CFR 50.46(a)(2). Although not specifically referenced by the Order, that specific authority is included within the Commission's general authority cited in the Order, which was explicitly issued under the authority of Sections 103, 161b, 1611, 1610, 182, and 186 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.202 and 10 CFR Part 50.

(See Order,Section VII.)

In your letter of August 14, 1996, you state that you "do not dispute that 10 CFR 50.46(a)(2) authorizes the NRC to impose the limitation on the power level at which Maine Yankee operates."

With respect to your questioning the authority of the Commission to permit operation of Maine Yankee at all, the choice of an appropriate mechanism for correcting an apparent violation rests within the sound discretion of the agency, and the paramount concern in exercising that discretion is public health and safety (Petition for Emergency and Remedial Action, CLI-78-6, 7 NRC 400, 405-406 (1978); See also Advanced Medical Systems, Inc., CLI-94-6, 39 NRC 285, 312-313 (1994)).

The staff was satisfied that Maine Yankee would be operated safely at the reduced power level, in accordance with 50.46(a)(2),

but did not perform an independent SBLOCA analysis because it was determined to be unnecessary with the restrictions to be imposed.

Specifically, with the imposed power penalty, the licensee's approved large-break loss-of-coolant accident analysis bounded credible design-basis accidents.

The Order contains an extensive discussion of the safety basis for the staff's conclusion that power operation with the imposed restrictions did not pose an undue risk to public health and safety.

Regarding your question as to the view of the Office of the General Counsel (0GC), you should be aware that 0GC provided advice and counsel to the staff of the Office of Nuclear Reactor Regulation (NRR) during the development of the Order and that, in 0GC's view, the Order is legally sufficient. Allowing Maine Yankee operation up to 90%, notwithstanding nonconformance with TMI items II.K.3.30 and II.K.3.31, was considered during the development of the Order.

I hope this information will help resolve your concerns about interim operation of Maine Yankee.

Sincerely, k

Shirley Ann Jackson cc:

Senator Cohen Senator Snowe Senator Lieberman Senator Biden Representative Dingell Representative Markey I

y g

Mr. Henry R. Myers Regarding your statements as to informing the public of the governing regulations and the necessity of a small-break loss-of-coolant analysis to be performed in this matter, I would agree that the staff could have been more clear as to the specific regulations in question. Nevertheless, it is clear that 10 CFR 50.46(a)(2) provides the Director of the Office of Nuclear Reactor Regulation with the authority to impose restrictions on reactor operations to ensure that the criteria of 10 CFR 50.46(a)(1) are met.

I do note that the staff's analysis and technical basis are comprehensive and support the order.

I trust you will appreciate that the Commission has followed this matter closely and would not hesitate to intervene should any improprieties arise.

Thank you for your expressions of concern and I trust you find my views responsive to your concerns.

Sincerely, (Original Signed By)

Shirley Ann Jackson I

cc:

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ACTlDif EDO Principal Correspondence Control jFROM:.

DUE: 08/29/96 EDO CONTROL: GT96627 DOC DT: 08/10/96 j

Hanry Myers FINAL REPLY
& 8/14/96

'TO:

Chairman Jackson FOR SIGNATURE OF :

    • PRI CRC NO: 96-0887 Chairman Jackson DESC:

ROUTING:

MAINE YANKEE Taylor Milhoan Thompson Blaha Cyr, OGC HMiller, RI DATE: 08/16/96 ASSIGNED TO:

CONTACT:

I (y,\\00RMAb"D

~

~ ~

_ _ _ _ _. _.~ Rus s ell ~~

SPECIAL INSTRUCTIONS OR REMARKS:

Raf. GT96559.

Coordinate with OGC.

NRR RECEIVED:

AUGUST 16, 1996 NRR ACTION:

DRPE:VARGA ACTION c

NRR ROUTING:

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N"^$!^

DUE To ti DIRECTOR'S OFFIC ZIMMERMAN GRIMES

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B0HRER g

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e OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET PAPER NUMBER:

CRC-96-0887 LOGGING DATE: Aug 16 96 ACTION OFFICE:

EDO/OGC AUTHOR:

HENRY MEYERS AFFILIATION:

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