ML20236D054
| ML20236D054 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/22/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236D051 | List: |
| References | |
| NUDOCS 8710270465 | |
| Download: ML20236D054 (1) | |
Text
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- I A y I
l ENCLOSURE l'
- 6 SAFETY EVALUATION BY THE OFFICE _0F NUCLEAR REACTOR REGULATION
- RELATING TO COMPUTER C3 DES FIBWR A M #E?RAN-TCPPECO L
PHILADELPHIA ELECTRIC C0& M!%
PEACH M)TTOM UNITS 2 AND 3 1
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00 CRIT. WQ 50-277 & 50-C78 q
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By letter dated A(uguM29,1986, the PhiladelphfC Electric Company (PECo) submitted two topical reports, PEC0-FMS-0001 <" Steady State Thermal-Hydraulic Analysis of Peach Bettom Units 2 ud ilusing'the.FIBWR Computer Code" and t~ w^-
PEC0-FMS-0002, "Metho'd for Transient'Critica1 Power Ratios for Boiling Water Reactors (RETRAN-TCPPECO)".:^The Office of Ne dear Reactor Regulation, NRC,
.has utilized Schnical UFsistance by the Idaho Nati(nal Engineering Laboratory (INEWin the deview of the licensee's submittals. The NRC he reviewed the Technial Eva@ tion Report (TER) on the evaluation which is in 4,nendix A of this(5fetyEvaluation(M). The staff concues in the yscemendations made by INEL Jad finds that the PEco methods are acceptable for reference in licensing anaV ses under the cond6tions stipulated. The conditiori are identified in Section 5 of the attached TER and are Westated as follows:
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(1)
In the use of.RE1AAN-TCPPECO, conservative values that account for uncertainties in hiput parameters should be used for hot channel analyses.
Each reload application should demonstrate that th3 uncertainties in plant parameters are treated with,at least a 95 percent probability at a 95 dprcent confidence ?evel in accordance with Acceptance Criterion 1.0 of-Stadard Review Plan Se6 Son 4.4.
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(2) TheRETRANhotchannelnodalization(24axialnobes)forthePeachBotton 2 and 3 active cores is adequate based on sensitivity studies performed j
by PECo. Other Options and models tg ts used in the RETRAN system and j
hot channel analyses for Peach Bottom 2 and 3 she>uld be controlled by the user to ensure that only NRC-approved models are used.
Based on our review of the licensee's submittal and our r.vteactor's TER, the staff concludes that FIFM and RETRAN-TCPPEC0 are acceptable for Peach Bottom reload analyses when theJabove conditions are satisfied, j
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The following statementln SeMAon 3.2 of the appended TER mgading th,e GEXL 4
bo MCPR limit of 1.07 0 j
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"The limit of'1,0T isiused st4 account for uncer,tainty in the GEkU q
'/It correlation by assumingtboiling transition occurs if the HCDR is less -
7, than or equal to 1.07 instead of the mathematical limit of 1.0.".
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is herein expanded to indicate that the numerical limit of 1.07 is batad on a generic statistical calcu}a!RCto determine the MCPR such that S9// pt.rcent of the fuel rods in a reion t. ore would av. tid boiling transition'akkg transients affecting the entire core.
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