ML20085K992
| ML20085K992 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/11/1983 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20085K995 | List: |
| References | |
| TAC-52554, NUDOCS 8310210238 | |
| Download: ML20085K992 (3) | |
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Snippingport, PA 15077@od D,irector of Nuclear Reactor Regulation
/0nited States fluclear Regulatory Commission Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch flo. 1 Division of Licensing bashington, DC 20555
Reference:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Revised Cycle 4 Reload Safety Evaluation Report Gentlemen:
Enclosed are ten (10) copies of the Beaver Valley Power Station, Unit No.1 Revised Cycle 4 Reload Safety Evaluation Report (RSER).
By letter dated September 1,1983, we forwarded to you two pages of the RSER that had been revised - Table 1 and Figure 1.
These were revised to incorporate the new core loading pattern and describe the Region 6A fuel assembly placed in the core as a result of the one that had been damaged during placement of the upper internals following fuel shuffle. The referenced letter also advised that we would also forward the revised RSER text when complete. Since then tne entire RSER has been revised to not only include tne new core loading pattern but also to delete all reference and discussions of the Wet Annular Burnable Absorber (WABA) rods.
Standard burnable poison rod assemblies are being used for Cycle 4.
The RSER revisions have been side barred and are described as follows:
Table cf Contents applicable page numbers revised Section 1.2 General Description
- 1) description revised to include Region 6A
- 2) WABA description deleted Section 1.3 Conclusions the definition of end-of-life full power capability residual boron concentration has been revised from 0 to 10 ppa to zero ppm g 00 f F310210238 831011 PDR ADOCK 05000334 l
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Beaver Valley Power Station, Unit No.1
/
Docket No. 50-334, License No. DPR-66 4
-Revised Cycle 4 Reload Safety Evaluation Report Page 2 i
Section 2.1 Pechanical Design l{ WABA description deleted description revised to include Region 6A 2,
Section 2.2 Nuclear Design 1) description revised to include Region 6A
- 2) WABA description deleted-Section 2.3 Thennal and Hydraulic Design reference number 8 revised to reference number 7 Section 3.1 Power Capability i
reference number 9 revised to reference number 8
(
l Section 3.2 Accident Evaluation new dropped rod methodology discussion deleted Section 3.2.1 Kinetics Parameters WABA description deleted
)
S_ection 3.2.2 Control Rod Worths _
j WABf description deleted j
Section 3.2.3 Core Peaking Factors i
incorporated a discussion of the use of the new i
dropped rod methodology for Cycle 4 Section 5.0 References _
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- 1) deleted reference 3 WABA's WCAP-10021 l
2) revised the other reference numbers accordingly Table 1 Fuel Assembly Design Parameters O{f Region 4, 4A and 5 beginning of Cycle 4 burnups 1
WABA description deleted have been revised; they are now based on an end of Cycle 3 i
burnup of 10637 MWD /liTU i
Table 3 End-of-Cycle Shutdown Requirements and Margins i
- 1) Table 3A - WABA design deleted i
- 2) Table-3B - retitied to Table 3 i
Figure 1 Core Loading Pattern reference to WABA's deleted 4
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Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Revised Cycle 4 Reload Safety Evaluation Report Page 3 This revised RSER applies to Cycle 4 operation and is intended to supercede our initial RSER forwarded May 23, 1983.
Very truly ours, J. J.
arey Vice President, Nuclear cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 1
U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 i
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