ML19351D764
| ML19351D764 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/12/1974 |
| From: | Vandenburgh D YANKEE ATOMIC ELECTRIC CO. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| WYR-74-53, NUDOCS 8011180292 | |
| Download: ML19351D764 (4) | |
Text
Propostd Change No. 117 b
plement No. 1
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Telephone 366-9011 i
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m 780-390-0739 YANKEE ATOMIC ELECTRIC COMPANY Win,<-53 m.
20 Turnpike Rood Westborough, Mossochusetts 01581
.Ya_uxte December 12, 1974 3
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9 DEC 13 1974 c:
a United States Atomic Energy Commission d.Y L.S, g I
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Washington, D. C.
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Reference:
(1) License No. DPR-3 (Docket No. 50-29)
(2) Proposed Change No. 117, " Revised ECCS Analysis",
submitted to DOL /AEC on July 31, 1974 (3)
" Yankee Nuclear Power Station Revised Loss of Coolant He c. "
\\T Analysis", IAC analysis submitted to AEC on
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Janua: y 15, 1972
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" Additional information on the Possible Effects of s
Fuel Densification on Subsequent Operation of Yankee h/
Rowe Cycle X" Proprietary, submitted to the Atomic ge
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Energy Commission by Yankee Atomic Electric Company i.y, e
Y,A
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on October 17, 1973
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(5)
Non-Proprietary Version of Reference 4
Subject:
Failure of Low Pressure Safety Injection Pumps to Deliver the Flow Rates Assumed in the ECCS Analysis
Dear Sir:
Pursuant to Section 50.59 of the Commission's Rules and Regulations, the Yankee Atcmic Electric Company hereby submits the following supplement to Proposed Change No. 117 (Reference 2).
. PROPOSED CHANGE: Reference is made to Section D.2.c of the Technical Specifications, Appendix A of License No. DPR-3.
We propose to limit the peak linear heat rate to 11.60 kw/ft until a revised ECCS analysis, performed in accordance with Appendix K of 10 CFR Part 100, indicates otherwise.
REASON FOR CHANGE: Safety injection performance tests at the Yankee Nuclear Power Station have shown that pumped ECCS flow rate at runout conditions is less than the flow assumed in the ECCS analysis.
DESCRIPTION OF CHANGE:
It is requested that the following revision be made to the above mentioned section of the Technical Specifications of the referenced license.
"is. v._
8011180
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United' States Atomic Energy Commission December 12, 1974
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Attn: Directorate of Licensing Page Two Section D.2 Operating Limits
-c.
Thermal
_ Revise paragraph (1) to read as follows:
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" (1) At rated power, F the nuclear' heat flux hot channel-factor, f0r, the hottest point in the hottest ~ channel shall not exceed 2.41.
Furthermore, the peak linear heat ra,te during power operation shall not exceed 11.60 kw/ft.
.These values shall be checked every 1000 equiva-lent full power hours of operation utilizing data derived from core instrumentation."
SAFETY CCNSIDEPATIONS: It is our finding that the station safety injection pumps have not suffered a deterioration in their delivery capability; rather the pumped ECCS capacity at runout conditions assumed in the ECCS analyses is incorrect. Furthermore, until now, this discrepancy has been masked by use of an incorrect conversion factor in the ECCS flow test procedure reculting in artificially high ECCS flow rates. A conservative effects analysis has been performed by Yankee Atomic Electric Company to determine what additional plant limitations shoulgbgegprarily imposed to maintain
-previously demonstrated safety margins.
It is required that Yankee Rowe be operated according to the more limiting cf the Interim Acceptance Criteria gg),5i"a"na"lysiswasdone Y
Acceptance Criteria (FAC) analysis. The IAC with a factor of.9 or decay heat due to gamma redistribution of energy.
In the FAC analysis a more appropriate value of.87 was used. From
- figure 2E cf Reference 3, it is seen that'the peak clad temperature for the worst break was-not sensitive to the sensible heat init~. ally stored in the fuel but was dependent on the decay heat level. Consequently, adjusting the "IACanalysiswiththeappropriatefactorof.8g allowable linear heat rate beceres.14.1 kw/ft rather than 12.9 kw/ft This is less limiting than the 13.06 kw/ft value shown in the FAC analysis. Thus, possible additional plant restrictions were evaluated on the basis of the results of the FAC analysis.
The approach taken.was to examine the worst break size (the double-ended cold leg guillotine with a discharge coefficient of 0.6) and con-servatively determine the additional time required to bring the fluid.
inventory-in the reactor vessel to the point where the clad temperature-rise'is te:minated. A reduced linear heat rate which should yield the same peak clad temperature shown in Reference 2 was then calculated. The assumptiens made in this calculation are discussed below:
1.
The twc-train pumped ECCS flow at runout without the accumulator is ccnservatively estimated to be "2180 gpm rather than the 2480 gp= assumed in Reference 2;-
2.
During the accumulator injection phase of the worst break (double-ended cold leg guillotine with a discharge coefficient of 0.6) the LPSI pumps are not quite at runout. However, the full 300 gpm penalty was still applied duri this phase;
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RG CRIGINAL
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Un'ited' States Atomic Energy Commission December 12, 1974 Attn: Directorate of Licensing Page Three 3.
It is conservatively assumed that a reduction in the peak linear heat rate does not improve the shape of the. clad temperature transient during the non-linear metal-water reaction period; 4.
It is assumedLthat the clad temperature at-the initiation of the adiabatic heatup phase is not lowered by a reduction in the peak.
linear heat rate.
. Based on these assumptions, a new linear heat rate limit of 11.60 kw/ft was calculated.
The Yankee Nuclear Power Station is currently being operated at a power level such that the peak linear heat rate does not exceed 11.60 kw/ft. The plant will continue'to observe this limit until a revised ECCS analysis-indi-cates'otherwise.
.This supplement to Proposed Change No. 117 has been reviewed by the Nuclear-Safety. Audit and Review Committee.
SCHEDULE OF CHANGE: We respectfully request review of this supplement by the Commission as soon as possible.
Any questions regarding this supplement should be directed to Mr. A. E.
Ladieu at our Engineering Office, 20 Turnpike Road, Westboro, Massachusetts 01581 (area code 617) 366-9011, extension 2845.
Respectfully submitted, YANKEE ATOMIC ELECTRIC COMPANY w
Donald E. Vandenburgh Vice President COMMONWEALTH OF MASSACHUSETTS) r-
)ss.
COUNTY OF WORCESTER
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Then personally appeared before me, Donald E. Vandenburgh, who being duly sworn, did state that he -is a Vice President of Yankee Atomic Electric Company, that he is duly authorized to file, execute-and sign the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, and that the
-statements therein are true to the best of his knowledge and belief.
~ L. R Armand R.-Soucy-Notary Public.'
My Commission Expires September 9, 1977 4
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n P0Dg DEGINAL i
AEC DISTRIBUTION FOR PART 50 DOCKET MATERI AL (TEMPORARY FORM)
CONTROL NO: 12 % 2 FILE:
I FROM: Yankee Atomic Elec. Co.
DATE OF DOC DATE REC'D LTR TWX RPT OTHER Westborough, Mass. 01581 12-12-7h 12-15-74 X
D.E VWhm-ch TO:
ORIG CC OTHER SENT AEC PDR XX 3 signed 37 SENT LOCAL PDR ppt CLASS UNCLASS PRO? INFO INPUT NO CYS REC'D DOCKET NO:
XXX 40 50-29 DESCRIPTION: Ltr notarized 12-12-74 submitted ENCLOSURES:
as Supplement to Proposed Change No.117 re ECCS, bO.%'A t'
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