ML20236R840
| ML20236R840 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/12/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20236R843 | List: |
| References | |
| NUDOCS 8711240058 | |
| Download: ML20236R840 (2) | |
Text
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',~pg Telephone (412) 393-6000 Nuclear Group
$n$p$* port. PA 15077-0004 '
0 November 12, 1987
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U.: S. l Nuclear Regulatory. Commission iAttn: cDocument Control Desk.
LWashington, DC--20555
Reference:
. Beaver Valley Power Station,' Unit No. 1 H
Docket No'.
50-334, License No. DPR-66 Cycle ~7 Reload Safety Evaluation Report
. Gentlemen:
-Enclosed are ten-(10) copies of the Beaver Valley Power Station,
- Unit No.. 1 Cycle 7-Reload Safety Evaluation Report (RSER).
This report Edocuments an evaluation of the Cycle 7 reload design-including
- the affects of :10%. Steam Generator-Tube Plugging, Upflow Conversion
..and. Thimble ~ Plug Removal.
Compared to the Cycle 6 reload fuel (Region
'8 ). the following design differences have been incorporated into the Cycle 7-reload fuel (Region 9):
'1)I Fuel pellet. stack holddown ' springs exert a 4G axial force
- instead of a.6G axial force.
.2); Fuel pellets'have chamfered edges.
3)
Integrated Fuel ~-Burnable Absorber (IFBA) rods are used in lieu of Wet: Annular Burnable Absorbers-(WABA).
- 4) ' IFBAL: fuel-rods-contain a
lower. Helium backfill pressure compared to non-IFBA fuel rods to offset the effects of the Helium gas release'from the IFBA coating during irradiation.
z5): s Reload fuel has 6-inch axial blankets of natural uranium pellets that-are of. the same design as the enriched pellets except<that these pellets are not dished.
t Duquesne Light Company has performed a detailed review of the Cycle' 7 -RSER -including a
review of the core characteristics to determine those parameters affecting the postulated accidents de' scribed-in the UFSAR..
The consequences of those incidents described in the UFSAR which could potentially be affected by the l
reload core characteristics were reanalyzed, and we have verified that..the. reanalyses were performed in accordance with the NRC approved. methodology described in WCAP-9273-A, " Westinghouse Reload Safety Evaluation Methodology".
The affects of the reload on the design 4 basis and postulated incidents analyzed in the UFSAR were i
accommodated within the conservatism of the initial assumptions and do not. exceed any previously acceptable safety limits.
l l
I 8711.240058 871112 y4 lg DR ADOCK'O
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'::Benv;r VallGy Pow 3r Stntion, Unit No.
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1 Dockit'No. 50-334, Lic n23 No. DPR-66 J
Cycle 17 Reload Safety Evaluation Report Page-2 LNo Technical Specification Char.ges are required as a result of
'theLcycle'7 reload design or the RSER.
The NRC approved dropped-rod methodology used for previous cycle design evaluations' was also used for the Cycle 7 design evaluation and1 confirmed that-the DNB design basis is met for all dropped-rod
. events initiated from full' power.
Therefore, no restrictions on rod
- Leontrol, either manual rod control or restricted rod insertion limits when in ' automatic rod control above 90% power are required for Cycle 17 ' operation.
The-reload. core design will be ' verified by performing the standard Westinghouse reload core startup physics tests.
The results of the following startup tests will be submitted in accordance with Technical Specification 6.9.1.3:
1.
Control rod drive tests and rod drop time measurements.
2.
Critical boron concentration measurements.
3.
-Control: rod bank worth measurements.
a
'4.
Moderator temperature coefficient measurements.
~
5.
Startup.. power distribution measurements using the 1
incore flux mapping system.
.The Beaver Valley Onsite Safety Committee (OSC) and the Duquesne 1'
Light -company. Offsite Review Committee (ORC) have reviewed this RSER
.and determined that the Cycle 7 reload core design will not adversely affect the' safety of the plant and does not involve an unreviewed i
safety question.
Very truly yours, a
Lr D. Sieber Vice President, Nuclear
- cc:
Mr. F. I. Young, Sr. Resident Inspector (Unit 1)
Mr. W. T. Russell,-NRO Region I Administrator Mr. P. Tam,: Project Manager
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