ML20062E396
| ML20062E396 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/03/1982 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| TAC-48707, NUDOCS 8208100091 | |
| Download: ML20062E396 (4) | |
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Telephone (412) 4564000 Nuclear Division August 3, 1982 P.O. Box 4 Shippingport, PA 15077 @ 04 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. l Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Additional Information:
Proposed Technical Specification Change No. 66 Gentlemen:
This letter responds to your staf f request that we provide addi-tional justification related to our original submittal of proposed Technical Specification Change No. 66.
Attachment A provides just-ification for changing the FoH multiplier from 0.2 to 0.3.
The information stated in Attachment A was received from Westinghouse and is identical to the information given to Portland General Electric for submittal to the NRC in order to support their application for the 0.3 multiplier change. The NRC approved the FoH multiplier change for the Trojan plant based on the additional infor-mation that was submitted.
As stated in the attachment, Figures 2.1-1, 2.l-2 and Table 2.2-l are also changed as a result of the 0.3 multiplier changes as previously subtrit ted.
If you have any questions regarding this response, please contact my office.
Very tr ly yours, J. J. Carey Vice President, Nuc lea r cc:
Mr. W. M. Troskoski, Resident Inspector
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U. S. Nuclear Regulatory Commission
.O Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 8208100091 820803 PDR ADOCK 05000334 P
,8 ATTACHMENT A
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ANALYSIS FCR A REVISED F g
LIMIT AT LESS THAN RATED THERMAL POWER Historically, increasing the allcwable F?. with aecreasing ocwer has been n
cermitted by ali previously approved Westingnouse cesigns.
Tne increase is permitted by the DNS protection setpoints and allows for radial pcwer distribution cnanges with rod insertion to the insertion limit.
t TheresultsoftheBeaverValleyUnit1F]g Tecn Scec limit analysis indicate that the limit may be modified by changing the limit slope from 0.2 to 0.3 at reduced power, resulting in the following relationship:
F 1 1.55 [1.0 +.3 (1-P)] O -RBP(BU)]
H where P = fraction of rated thermal power.
Note that the only change from the current F Tech Spec is the multiolier on the quantity (1-P) from 0.2 H
to 0.3.
No change is made in the F limh at full power.
g This change is recommended for Beaver Valley to allow optimization of the core N
loading pattern by minimizing restriction on the F at low power.
This change tH will also minimize the probability of making rod insertion limit changes to satisfy peaking factor criteria at low Dower with the control rod banks at the insertion limit.
Core CNB limits were generated for Esaver Valley Unit 1 for the increased N
allowable F'H at reduced power levels. As a result of the char.ges in Core DNB limits, the Core Safety Limits (Figure 2.1-1 and 2.1-2 of the Technical Specifications) changed.
Only minimal changes had to be made to the Core Safety Limits because at most conditions below full power, the restriction that the average enthalpy at the vessel exit is less than the enthalpy of saturated liquid is more limiting than DNB considerations.
This vessel exit entnalpy limit is not core peaking factor dependent.
The new Core
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- Safety Limits were used in the safety evaluation for Cycle 3 and tne results snow that all limits are met.
No change to K,K_,K.K, or K: factors is i
4 3 reauired in Section 2.2 of tne Technical Specifications, as a result of the new core and axial offset limits.
Therefore, no cnanges to tne overpower and over temperature celta-T setooints are necessary and hence no accident reanalysis is recuired.
As a result of the enange to a.3 multiplier, the F(;I) function is slightly more limiting.
Therefore, in Table 2.2-1, page 2-9 of the Beaver Valley Unit Technical Soecifications, items (i) and (iii), +13 has been replaced by +11.
These modifications were msde in WCAP-9500 ano approved by the f4RC with the additional technical supporting information supplied by NS-TMA-2323, (letter from Anderson to Miller, dated October 24,1980.)
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WESTINGHOUSE PROPRIETARY CLASS 2 BFAVER VALLEY l (DLW) CYCLE 3 CONSERVATIVE CALCULATION OF.ENTHALPY RISE FACTOR WITH POWER LEVEL AND TECHNICAL SPECIFICATIONS LIMITS 2.0 r-Ex s,
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