ML19347D899
| ML19347D899 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 03/25/1981 |
| From: | Randazza J Maine Yankee |
| To: | |
| Shared Package | |
| ML19347D900 | List: |
| References | |
| FMY-81-43, NUDOCS 8104140428 | |
| Download: ML19347D899 (3) | |
Text
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Propcsed Change to. 82 MAIRE
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, N 2 14 v-United States Nuclear Regulatory Commission Washington, DC 20555 3'//g i;~
Attention:
Office of POclear Reactor Regulation
References:
(a)
License No. DPR-36 (Docket No. 50-309)
(b) Perrin, J. S., et. al., " Maine Yankee tbclear Plant Reactor Pressure Vessel Surveillance Program: Capsule 263",
BCL-585-21, Battelle Columbus Laboratories, December 21, 1980.
(c) Hawthorne, J. R., " Notch Ductility Degradation of Low Alloy Steel With Low-to-Intermeciate Neutron Fluence Exposures",
NUREG/CR-1053; NRL Report 8357, Naval Research Laboratory, Washington, DC, January 14, 1980.
(d) Hawthorne, J. R., et. al., " Evaluation of Commercial Production A533-B Plates and Welo Deposits Tailored for Improved Radiation Cmbrittlement Resistance", Procerties of Reactor Structural Alloys After Neutron or Particle Irradiation, ASTM STP 570, American Society for Testing and Materials, 1975, pp.83-102.
Dear Sir:
Subject:
Modification to Maine Yankee Technical Specifications Pursuant to Section 50.59 of the Commission's Rules and Regulations, Maine Yankee Atomic Power Company hereby proposes the following modifications to Appendix A of the Operating License.
PROPOSED CHANGE Reference is made to the Technical Specifications contained in Appendix A to Operating License No. OPR-36 issued to the Maine Yankee Atomic Power Company and to Reference (b). We propose to modify the current Technical elon 4 o %t?
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Lhited States toclear Regulatory Commission March 25,1981 Attention: Office of Nuclear Reactor Regulation Page Two Specifications as follows:
A.
Replace Figures 3.4-2 and 3.4-3 with the attached revised Figures
- 3. 4-2 and 3.4-3.
REASON FOR CHANGE During the Maine Yankee Ofcle 4/5 refueling catage, a reactor vessel wall surveillance capsule was removed from the Maine Yankee reactor and sent to Battelle Columbus Laboratories for analysis.
The results of that analysis (Reference [b]) showed a greater than anticipated fluence experienced by the reactor vessel wall.
The difference between the predicted results and that found by Battelle is believed to be due to the methodology and/or calculational errors used in the original predictions.
Maine Yankee believes the Battelle results are correct based on a comparison of the Battelle results with the results of material property changes exhibited by other actual Maine Yankee vessel material utilized in test reactor programs (References [c] and [d]).
Reference (b) also provided a revised set of curves for predicted fluence versus power history.
These curves were derived using a more sophisticated, complex computer code than is believed to have been used in the original predictions.
Tnese revised curves will be used in conjunction with the fluence versus RTNDT shift curve of Regulatory Guide 1.99, Revisior.1, April 1977 to predict the increase in RTNOT due to neutron irradiation.
This increase in RTNDT will then be factored into the operating limit curves for heatup, cooldown and hydrotest of the reactor coolant system.
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It should be noted that analyses of actual Maine Yankee reactor vessel i
material (References [b], [c] and [d]) have all shown the curves of Regulatory l
Guide 1.99 to be quite conservative for Maine Yankee.
However, Maine Yankee believes it prudent to incorporate this additional conservatism in the generation of its normal operating limitations.
BASIS FOR CHANGE l
Appendix H to 10 CFR 50 requires the periodic removal and analysis of reactor vessel material surveillance capsules.
The results of these analyses are used to verify original predictions or update them as necessary to assure the stresses imposed upon the reactor vessel are within design limitations.
l SAFETY EVALUATION The changes to the Technical Specifications are necessary to ensure that l
the reactor vessel is operated under temperature and pressure conditions where brittle fracture will not occur.
It is concluded that these changes do not l
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United States Nuclear Regulatory Commission March 25,1981 Attention: Office of Nuclear Reactor Regulation Page three i
present any significant hazads not described in the safety analysis report and do not involve an unreviewed safety question as described in 10 CFR 50.59.
This change has been reviewed by. the Maine Yankee Nuclear Safety and Audit Review Committee.
FEE DETERMINATION This proposed change requires an approval that involves a single safety i
issue and is deemed not to involve a significant hazards consideration.
For these reasons, Maine Yankee Atomic Power Company proposes this change as a Class III Amendment.
A payment of $4,000 is enclosed.
j SCHEDULE OF CHANGE j
The changes described above will be incorporated into the Maine Yankee l
Technical Specifications upon receipt of your approval.
We trust you will find this information satisfactory; however, should you I
desire additional information, feel free to contact us.
Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY A,
m-y i
J. B. Randaz j
Vice President COMMONWEALTH OF MASSACHUSETTS) i i
)ss MIDDLESEX COUNTY
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l Then personally appeared before me, J. B. Randazza, who, being duly sworn, did state that he is a Vice President of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Maine Yankee Atomic Power Company, and that I
the statements therein are true to the best of his knowledge and belief.
l Robert H. Groce Notary Public l
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