ML20236D048

Forwards Safety Evaluation & Technical Evaluation Rept Fibwr & Tcppeco Computer Programs in Support of Util Methods for Use in Part of Core Reload Analyses for Plant

ML20236D048
Person / Time
Site:	Peach Bottom
Issue date:	10/22/1987
From:	Martin R Office of Nuclear Reactor Regulation
To:	Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Shared Package
ML20236D051	List: ML20236D048 ML20236D054 ML20236P511
References
TAC-62772, TAC-62773, TAC-62774, TAC-62775, NUDOCS 8710270464
Download: ML20236D048 (3)

Text

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Cetober;22,1987L dL .i_ .

• Docke't Nos.: I50-277/50-278 1 3 S.

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lMri Edward Gi Bauer,iJr.  ;

Vice President and General Counsel L -Philadelphia Electric. Company = '

2301. Market Street .

philadelphia,(Pennsylvania 19101.

Dear Mr. Bauer:

, 3.

l

SUBJECT:

' SAFETY EVALUATION FOR REPORTS-PEC0-FMS-0001 ND'PEC0-FMS-0002 FOR CORERELOADANALYSES_(TACN05.162772,62774,62773'AND;62775)1 The-NRC staff and its consultants at the Idaho Nationa1' Engineering Laboratory have ~ reviewed the Philadelphia Electric Company' reports on the computer. program '

analyses methods intended to be.used in part of the PECO core reload analyses  ;

for the Peach Bottom Atomic Power Station.' The reports, PEC0-FMS-0001, " Steady '

F  ; State Thermal Hydraulic AnalysesLof Peach. Bottom Units 2 and 3:using the'FIBWR Computer Code," and PEC0-FMS-0002L " Method;for Trans'ient Critical Power Ratios.

-for Boiling Water Reactors:(RETRAN-TCPPECO)," were submitted by letter dated-

? August 29,.1986.- As concluded-in the' safety evaluation-in the. enclosure, the staff-finds that the PEC0 methods:are acceptable for..use:in licensing application under. the limitation' stipulated.in the ~ evaluation.

Sincerely,c

/s/. "

Robert E. Martin,. Project Manager Project Directorate I-2 Division of Reactor Projects  ;

Enclosure:

As stated ,

DISTRIBUTION:

!SDocketdileg RMartin/RClark

.NRC PDR/LPDR OGC-Bethesda

-PDI-2 Reading' EJordan SVarga/BBoger JPartlow

• WButler - ACRS (10)

M0'Brien FWitt-

MMcCoy-

Previously concurred

• i PJI-2/PM* PDI-2/D*

Nfttht:mr WButler 0/22/87- 10/22/87 ,

4 8710270464 871022 PDR ADOCK 050 g 7 e .

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s d j Docket Nos.: 50-277/50-278 - l Mr.4 Edward G. Bauer, Jr..

Vice President'and General younsel 7' m , i c "

Philadelphia Electric Company

.2301 Market Street .

Philadelphia, Pennsylvania 1910F ,

1

Dear Mr.,

Bauer: q  !

1

SUBJECT:

' SAFETY EVALUATION.FOR REPORTS PEC0-FMS-0001 AND PECD-FMS-0002 FOR -

1

.C0RE RELOAD' ANALYSES (TAC NOS. 62772, 62774, 62773 AND 62775)

, l The NRC staff and its consultants at the Idaho National Engineering Laboratory j have reviewed the Philadelphia Electric Company reports orj the computer program l' analyses methods. intended to'be used in part of the PECO core reload' analyses for the Peach Bottom Atomic Power Station. The reports, PEC0-FMS-0001, " Steady. i State Thermal Hydraulic Analyses of Peach Gottom. Units 2 andl3 using the FIBWR l

~ Computer Code," and PEC0-FMS-0002, " Method for Transient Critical Power Ratios ,

for Boiling Water Reactors (RETRAN-TCPPEC0)," where submitted by letter dated .h'j August 29, 1986. As concluded in the safety evaluation in the enclosure, the staff finds.that the PECO methods are acceptable for use in licensing application under the limitation stipulated in the evaluation. <

u Sincerely. -

j 1

Robert E. Martin, Project Manager Project Directorate I-2 Division of Reactor Projects i

Enclosure:

As stated DISTRIBUTION:  !

Docket File RMartin/RClark {

NRC PDR/LPDR OGC-Bethesda .

PDI-2 Reading EJordan , f SVarqa/BBoger JPartlow ' {

WButler ACRS (10) ,

M0'Brien FWitt ,

i MMcCoy 4

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i lhNmr t

/4 /27/87 Q/g87

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~g UNITED STATES -

F' i NUCLEAR REGULATORY COMMISSION

[* h  : $

WASHING TON, D. C. 20555 October 22, 1987 Docket Nos.: 50-277/50-278 Mr. Edward G.:Bauer, Jr.

Vice President and General Counsel Philadelphia Electric Company -

2301 Market Street Philadelphia, Pennsylvania 19101

SUBJECT:

SAFETY EVALUATION FOR, REPORTS PFC0-FMS-0001 AND PECO-FMS-0002 FOR CORE RELOAD ANALYSES (TAC N05. 62772, 62774, 62773 AND 62775)

The NRC staff and its consultants at the Idaho National Engineering Laboratory have reviewed the Philadelphia Electric Company reports on the computer program analyses methods intended to bp used in part of the PECO core reload analyses for the. Peach Bottom Atomic Pcwer Station. The reports, PECO-FMS-0001, " Steady State Thermal Hydraulic Analyses ,tf Peach Bottom Units 2 and 3 using the FIBWR Computer Code," and PECO-FMS-0002, " Method for Transient Critical Power Ratios for Boiling Water Reactors (RETRAN-TCPPECO)," were submitted by letter dated August 29, 1986. As concluded in the safety evaluation in the enclosure, the staff finds that the PECO methods are acceptable for use in licensing application under the limitstion stipulated in the evaluation, w

y

- , Sincerely,

\

/

' d t.W bert E. artin, Project Manager Project Directorate I-2 Division of Reactor Projects

Enclosure:

As stated

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