ML19289C503
| ML19289C503 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/20/1978 |
| From: | Stello V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19289C504 | List: |
| References | |
| NUDOCS 7901170049 | |
| Download: ML19289C503 (5) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
)
PORTLAND GENERAL ELECTRIC COMPANY
)
Docket No. 50-344 THE CITY OF EUGENE, OREGON
)
PACIFIC POWER & LIGHT COMPANY
)
)
(Trojan Nuclear Plant
)
EXEMPTION I.
s Portland General Electric Company, The City of Eugene, Oregon and Pacific Power & Light Company (the licensees) are the holders of Facility Operating License No. NPF-l which authorizes the operation of the nuclear power reactor known as Trojan Nuclear Plant (the facility) at steady reactor power levels not in excess of 3411 megawatts thermal (rated power). The facility consists of a desting-house Electric Corporation designed pressurized water reactor (PWR) located at the licensees' site in Columbia County, Oregon.
II.
In accordance with the requirements of the Commission's ECCS Acceptance Criteria 10 CFR 50.46, the licensees submitted on March 31, 1977 an ECCS evaluation for proposed operation using 17 X 17 fuel manufactured by 'the WestingSouse Electric Corporation. This evaluation included limits on the peaking factor. The ECCS performance evaluation submitted by the licensees was based upon an ECCS evaluation developed by the Westinghouse Electric Corporation (Westinghouse), the designer of the Nuclear Steam Supply S; stem 7 9 0117 0 0 <ff
Portland General Electric Company December 20, 1978 cc:
Mr. H. H. Phillips Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 Warren Hastings, Esquire Counsel for Portland Generel Electric Company 121 SW Salmon Street Portland, Oregon 97204 Mr. J. L. Frewing, Manager Generation Licensing and Analysis Portland General Electric Company 121 SW Salmon Street s
Portland, Oregon 97204 Columbia County Courthouse Law Library, Circuit Court Rocr.
St. Helens, Oregon 97501 Director, Oregon Department of Energy Labor & Industries Building, Rm. 111 Salem, Oregon 97310 Richard M. Sandvik, Esquire Counsel for Oregon Energy Facility Siting Counsel and Oregon Department of Energy 500 Pacific Building 520 SW Yamhill Portland, Oregon 97204 Michael Malmrose U. S. ' Nuclear Regulatory Commission Trojan Nuclear Plant P. O. Box 0 Rainier, Oregon 97048
--em
to do so for all licensing actions while the Board retains jurisdiction in the Control Building proceeding, regardless of whether or not any such licensing actions relate to that proceeding in any way.
Sincerely, h
/&
./ os ph R.
Gra
' Co usel for C St ff
Enclosure:
As stated cc w/ enclosure:
Service List for Control Building
. ~.
I T/,8tE 1 PCT Fn AFy AFzr02 AFFLECHT I F. MIN ofE50R afcp AFpr PCT ISE AF g AFACV IQ LIMIT.
Q S
F OTD Fq Analysis _
2 Loop Pt. Beach 1 2025 2.32
.16
.2 2.28 2.32 2.28
,01
,029 2.32 Pt. Reach 2 2025 2.32
.16
.2 2.28 2.32 2.28
.01 066 2.32 Ginna 1972 2.32 26
.2 2.32 2.32 2.32 053 2,32 rewaunee 2172 2.25
.03
.2
.05 2.13 2.25 2.13
.01 02 2.16 Pralrte Island 1/2 21u7 2.32
.01
.2 05 2.18 2.26 2.18
,01 02 03 2,24(+)
3 Loop North Anna 2101 2.32
.02
.2 2.14 2.32 2.14 2.14 Beaver Valley 2011 2.32
.15
.2 2.21 2.32 2.27
.036 2.31 Farley 1991 2.32
.24
.2 2.32 2.32 2.32
.01
.005 2.32 i
Surry 1 2177 1.85
.02
.2
.06 1.73 1.84 1.73
.03
.025
.023 1.81
~
Sorry 2 2177 1.85
.02
.2 06 1.73
- 1. M 1./3
.03
.025
.023 1.81 Turkey Point 3 2019' l.90
.14 0
.03 2.01 2.05 2.01
.020 2.03 Turkey Point 4 2195 2.05
.00
.2 05 1.90 1.91 1.90
.01 1.91 4 Icop Indian Point 2 2006 2 32
.11
.2 2.23 2.23 2.23
.01 2.24 Indian Point 3 2125 J.32
.07
.2
.06 2.25 2.19 2.19
.01
.03 2.23 Trojan 1975 2.32
.26
.2 2.32 2.32 2.32
.01
.037 2.32 541 &i 1 2135 2.32 06
.2 2.10 2.32 2.18
.01
.024 2.21 Zion 1/2
? ltN *
- 2,07 0
.03 2.01 2.01 2.04p)
Coot 1 2161*
1.90
.03 0
.03 1.90 1.93 1.90 1.90 Cook 2 2190* 2.10
.01 0
0 2.11 2.11 0
0 0
0 2.11 1
0 FT
- Credit in Fq for PCT margin to 2200 F limit.
Fzr02 - Metal Water Reaction penalty on F.
q FFLECHT-Credit in Fq or improvements to 15415 FLECHT Correlation.
f FPCT
- Staf f estimated Fq based on 22000F PCT limit.
i
/
FSE
- Westinghouse proposed Fq based on stored energy sensitivity studies.
' Denotes reanalysis at Fq old value error carrected.
- Denotes reanalyses at Fq old value, er ror corrected, accui.ulator Vol. Change of 100 ft. accumulator pressure of 650 psia.
3 b) These limits are applicable assuming Itcensee modif tes accumulator conditions as appropriate. I f not. Prairie i
Island 1/2 0 2.21. Zlen 1/2 Fq=1.9 1
9
References 1.
R. S. Doupall, U. fl. Rohsenow, " Film Boiling on the Inside of Vertical Tubes with Upward Flow of the Fluid at Lov Qualities",
MIT Report 9079-26, September 1963.
2.
EPRI Report !!P-525, "High Temperature Properties of Zircaloy-0xygen Alloy", Itarch 197 7.
3.
WCAP-9220, "Mestinghouse ECCS Evaluation flodel, February 1978 Version", February 1978.
4.
UCAP-8985
" Perturbation Technique For Calculatino ECCS Cooling Perforrr.ance", February 1977.
5.
Memorandun: Rosztoc7.y to Eisenhut and P.oss, " Metal-Uater Reaction Heat Generation Error in Westinghouse ECCS Evaluation !!odel Cor.puter Progran," April 7,1978.
6.
T. tiorita, et al., " Power Distribution Control and Load Follouina Procedures," UCAP-8385 (Proorietary) and UCAP-8403 (Non-Proprietary),
Septenber 1974.
G o
4
. for this facility. The Westinghouse ECCS Evaluation Model had been previously found to confom to the requirements of the Commission's ECCS Acceptance Criteria,10 CFR Part 50.46 and Appendix K.
The evaluation indicated that with the peaking factor limited as set forth in the evaluation, and with other limits set forth in the facility's Technical Specifications, the ECCS c001ing perfomance for the facility would confom with the criteria contained in 10 CFR 50.46(b) which govern calculated peak clad temperature, maximum cladding oxidation, maximum hydrogen generation, s
coolable geometry and long-term cooling.
On March 23, 1978 Westinghouse informed the Nuclear Regulatory Commission (NRC) that an error had been discovered in the fuel rod heat balance equation involving the incorrect use of only half of the volumetric heat generation due to metal-water reaction in calculating the cladding temperature. Thus, the LOCA analyses previously submitted to the Commission by licensees of Westinghouse reactors were in error. The staff promptly detemined that no immediate action was required to assure safe operation of these plants. Moreover, the Trojan facility has not operated since March, 17, 1978.
The error identified would result in an increase in calculated peak clad I
temperature, which, for some plants, could result in calculated tempera-tures in excess of 2200*F unless the allowable peaking factor was reduced l
somewhat. Westinghouse identified a number of other areas in the approved model which Westinghouse indicated contained sufficient conservatism to offset the calculated increase in peak clad temperature resulting from the
~
correction of the error noted above. Four of these areas were generic, applicable to all plants, and a number of others were plant specific.
As outlined in the attached Safety Evaluation Report (SER), the staff deter-mined that some of these modificatio would be appropriate to offset to some The attached SER extent the penalty resulting from correction of the error.
sets forth the value for each modification applicable to each facility.
Revised computer calculations correcting the error, noted above, and incorporatinP the modifications described in the SER have not been run for each plant. However, the various parametric studies that have been made for various aspects of the approved Westinghouse model over the cour se of time provide a reasonable basis for concluding that when final revised cal-culations for the facility are submitted usi.7g the revised and corrected nr; del, they will demonstrate that when operated at the peaking factors set forth in the SER operation will conform to the criteria of 10 CFR 50.46(b). Such revised calculations fully conforming to 10 CFR 50.46 have not yet been completed by Westinghouse for the Trojan They are expected to be completed and submitted before April,1979.
facility.
Operation of the facility would nevertheless be technically in non-confonnance with the requirements of 550.46, in that specific computer runs for the particular facility employing revised models with the Westinghouse metal-water error corrected and with the proposed model changes considered as a complete entity will not be complete for some
tine. However, operation as specified in this Exemption will assure that the ECCS system will conform to the performance criteria of 550.46.
Accordingly, while the actual computer runs for the specific facility are carried out to achieve full compliance with 10 CFR 550.46, operation of the facility will not endanger life or property or the common defense and security.
s In the absence of any safety problem related to this ECCS matter associated with operation of the facility during the period until the computer com-putations are completed, there appears to be no public interest consideration favoring restriction of the operation of the captioned facility. Accordingly, the Commission has determin;d that an exemption in accordance with 10 CFR 550.12 is appropriate. The specific exemption is limited to the period of time necessary to complete computer calculations.
IV.
Copies of the Safety Evaluation and the following documents are available for inspection at the Commission's Public Document Room at 1717 H Street, Washington, D. C.
20555, and are being placed in the Commission's local public document room at the Columbia County Courthouse Law Library, Circuit Court Room, St. Helens, Oregon 97501.
(1) Letter from Westinghouse to NRC dated April 7,1978.
(2) Letter from Portland General Electric Company, to Mr. A. Schwencer, Operating Reactors Branch fl, dated April 12, 1978.
. (3) This Exemption in the matter of Trojan Nuclear Plant.
Wherefore, in accordance with the Commission's regulations as set forth in 10 CFR Part 50, the licensees are hereby granted an exemption from the re-quirements of 10 CFR 550.46(a)(1) that ECCS perfomance be calculated in accordance with an acceptable calculational model which conforms to the provisions in Appendix K, without errors discussed herein.
This exemption is conditioned as follows:
s As soon as possible, but not later than April 1,1979, the licensees shall submit a reevaluation of ECCS cooling per-fonnance calculated in accordance with the Westinghouse Evaluation Model, approved by the NRC staff and corrected for the errors described herein.
FOR THE NUCLEAR REGULATORY COMMISSION f'fG-
/
Victor Stello, J.. Director Division of Operating Reactors Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 20th day of December,1978
6 P
Holmes Alexander Atomic fuel Adyance is Natural Tide. 'alitytheseaddv
+
WASHINGTON - Despite popu. not as the misinformation has it. West Germany, France and Russia liut in' re lar and pseudo-historic misinfor-The president, who called himself a are fit possessors and users of to the sentence of extinction under:
mation, King Canute (995-1035), a nuclear engineer during the cam-plutonium, but he has filed strong ' which all men, individually and' Danish prince who won the crown paign on the grounds 'that he demurrers in the cases of India, collectively, live out their years.U 4 of Britain by conquest and ruled by studied to be a nuclear sailor, is Argentina and Brazil, among.-
cruelty until a pilgrimage to Rome very w rong in his present attitude, ; others.
. Ignorance in the use of death-4 totally reversed his savage charac.
He is wrong in giving credence to ?.Ilo has been somewhat contvocal dealing materials is more perilous ter, never tried to stop the waves to the fright that plutonium, a product as to Israel,'which has a scientific than knowledge, and the world has stop rising r.t his command.
,of processing the atomicfuel fs not4 fron curtain'of its own, and to Red made more progress under the dis-To the contrary,he used the ruse h only prohibitively dangerous to China which is trying to buy the ciplines of theinternational Atomic -
that his power was unlimitd. He experiment away from turning itd work with,butis a mere collegelab 1 plant equipment from France as a rebuke to flatterers who said which needs U.S. approval to make proved that a natural tide has no into an U-bomb. Spokesmen here at necessary purchases from Westin.7 peace, than any of the disarma-regard for human kingship, and, the Atomic Industrial Forum lioot, ghouse.
p d 8 g ment treatics.
according to his biographer, Hun-at this amateurish superstition.,
tington, Jet the crown aside and, The separated plutonium is well
<It strikes me tilat the time has? As Churchill foresaw the 'atomis come for Mr. Carter to emulate the. weapon was more likely to dictate!
never (ore it again.
~ within controlof modernscientists,.real King Canute; demonstrate to ; carth-shatte One' modern application of this ! knowledge of its priorities is a peace of mutual terror than an, legend could be President Carter. worldwide and it is invaluablo be one and allithat he cannot com and his attempt to halt the advance l: cause it is the only man-made re-mand the tides of nature, and even.the equipment of South Korea with '
of nuclear power plants in poor ? newable fuel that is known.
to doff the crown he wears as the tactical nuclear weapons is a po-Mr. Carter is wrong also in the. ruler of the world's greatestindust-tent ~ dissuader to its northern countries.
neighbor. It's even doubtful that. -
The advance of atomic fuelis a : snobbish attitude that only the rich.r.ial nati "*
h s
i.the Chiefs of Staff would advise ani natural tide if there ever was one,7 and powerful nations have rightful T'!The mere existence of warlike attack on a nuclear armed Cuba!
and Mr. Carterwould be wiserif he f claims on plutonium. He concedes explosives, from; gun powder,to behaved as Canute actually did g that Britain, the United States,", plutonium carry a certain danger, tion.pt under the direst provocaJ exce A,
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