ML19344B502: Difference between revisions

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| number = ML19344B502
| number = ML19344B502
| issue date = 10/16/1980
| issue date = 10/16/1980
| title = Withdraws 750617 Application for Amend of Licenses DPR-44 & DPR-56,as Supplemented by 770225 Ltr.Reactor Core Design Improvements Implemented at Recent Refueling Outages Are Providing Desired Control Rod Withdrawal Flexibility
| title = Withdraws 750617 Application for Amend of Licenses DPR-44 & DPR-56,as Supplemented by .Reactor Core Design Improvements Implemented at Recent Refueling Outages Are Providing Desired Control Rod Withdrawal Flexibility
| author name = Bradley E
| author name = Bradley E
| author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
| author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Line 19: Line 19:
=Text=
=Text=
{{#Wiki_filter:_.
{{#Wiki_filter:_.
i .
i QJ PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. DOX 8699 PHILADELPHI A. PA.19101 EDWARD G. BAUE3, JR.
QJ PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. DOX 8699 EDWARD G. BAUE3, JR.                     PHILADELPHI A. PA.19101 ND G NE   L   UNsEL                       l215) 841 4000 EUGENE J. BRADLEY Assoca Art oENEnAL coWNsEL DONALD BLANKEN
ND G NE L
              ' "^
UNsEL l215) 841 4000 EUGENE J. BRADLEY Assoca Art oENEnAL coWNsEL DONALD BLANKEN ICKIRKdE"'"'
ICKIRKdE"'"'                                           Oc tober 16, 1980 T. H. M AHER CORNELL AssesTANT GEN RAL COUNSEL EDWARD J. COLLEN. JR.
Oc tober 16, 1980
' "^
T. H. M AHER CORNELL AssesTANT GEN RAL COUNSEL EDWARD J. COLLEN. JR.
JOHN F. KENNEDY. JR.
JOHN F. KENNEDY. JR.
l         ass 3sTANT COUNSEL 1
l ass 3sTANT COUNSEL 1
l Mr. Robert W. Reid, Chief Operating Reactor Branch #4 Division of Licensing United States Nuclear Regulatory Commission Washington, D. C. 20555 Re:     Peach Bottom Atomic Power Station Units 2 and 3 l                           Docket Nos. 50-277 and 50-278 l
l Mr. Robert W. Reid, Chief Operating Reactor Branch #4 Division of Licensing United States Nuclear Regulatory Commission Washington, D. C.
20555 Re:
Peach Bottom Atomic Power Station Units 2 and 3 l
Docket Nos. 50-277 and 50-278 l
License Amendment Application APRM Rod Block and Scram Curves
License Amendment Application APRM Rod Block and Scram Curves


==Dear Mr. Reid:==
==Dear Mr. Reid:==
f I
f I
L                                   Our Application for Amendment of Facility Operating l                 Licenses DPR-44 and DPR-56 filed on June 17, 1975, as l                 supplemented by letter dated February 25, 1977, requested l                 changes to the Peach Bottom Technical Specifications which
L Our Application for Amendment of Facility Operating l
!                  would revise the APRM rod block and scram trip setting l                 equations. These changer were requested to permit greater flexibility for withdraw.1 of control rods at reduced core
Licenses DPR-44 and DPR-56 filed on June 17, 1975, as l
(                 flow conditions and theraby reduce reactor startup time.
supplemented by {{letter dated|date=February 25, 1977|text=letter dated February 25, 1977}}, requested l
l                                   Reactor core design improvements have been implemented l                 at each of the most. recent Unit 2 and 3 refueling outages.
changes to the Peach Bottom Technical Specifications which would revise the APRM rod block and scram trip setting l
l                 - These improvements are providing the desired control rod with-drawal flexibility, therefore the referenced license amendment l
equations.
request is not needed at this time. Therefore, we withdraw the referenced license amendment request for revision of the APRM rod block and scram trip setting equations.
These changer were requested to permit greater flexibility for withdraw.1 of control rods at reduced core
Very truly yours,
(
                                                                -e k
flow conditions and theraby reduce reactor startup time.
80102103R7                                                 Eugene J. Bradley
l Reactor core design improvements have been implemented l
                  -EJBimk
at each of the most. recent Unit 2 and 3 refueling outages.
                                        .}}
l
- These improvements are providing the desired control rod with-drawal flexibility, therefore the referenced license amendment request is not needed at this time.
Therefore, we withdraw l
the referenced license amendment request for revision of the APRM rod block and scram trip setting equations.
Very truly yours, k
-e 80102103R7 Eugene J. Bradley
-EJBimk
.}}

Latest revision as of 11:30, 24 December 2024

Withdraws 750617 Application for Amend of Licenses DPR-44 & DPR-56,as Supplemented by .Reactor Core Design Improvements Implemented at Recent Refueling Outages Are Providing Desired Control Rod Withdrawal Flexibility
ML19344B502
Person / Time
Site: Peach Bottom  
Issue date: 10/16/1980
From: Bradley E
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Reid R
Office of Nuclear Reactor Regulation
References
NUDOCS 8010210329
Download: ML19344B502 (1)


Text

_.

i QJ PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. DOX 8699 PHILADELPHI A. PA.19101 EDWARD G. BAUE3, JR.

ND G NE L

UNsEL l215) 841 4000 EUGENE J. BRADLEY Assoca Art oENEnAL coWNsEL DONALD BLANKEN ICKIRKdE"'"'

Oc tober 16, 1980

' "^

T. H. M AHER CORNELL AssesTANT GEN RAL COUNSEL EDWARD J. COLLEN. JR.

JOHN F. KENNEDY. JR.

l ass 3sTANT COUNSEL 1

l Mr. Robert W. Reid, Chief Operating Reactor Branch #4 Division of Licensing United States Nuclear Regulatory Commission Washington, D. C.

20555 Re:

Peach Bottom Atomic Power Station Units 2 and 3 l

Docket Nos. 50-277 and 50-278 l

License Amendment Application APRM Rod Block and Scram Curves

Dear Mr. Reid:

f I

L Our Application for Amendment of Facility Operating l

Licenses DPR-44 and DPR-56 filed on June 17, 1975, as l

supplemented by letter dated February 25, 1977, requested l

changes to the Peach Bottom Technical Specifications which would revise the APRM rod block and scram trip setting l

equations.

These changer were requested to permit greater flexibility for withdraw.1 of control rods at reduced core

(

flow conditions and theraby reduce reactor startup time.

l Reactor core design improvements have been implemented l

at each of the most. recent Unit 2 and 3 refueling outages.

l

- These improvements are providing the desired control rod with-drawal flexibility, therefore the referenced license amendment request is not needed at this time.

Therefore, we withdraw l

the referenced license amendment request for revision of the APRM rod block and scram trip setting equations.

Very truly yours, k

-e 80102103R7 Eugene J. Bradley

-EJBimk

.