ML20041G401
| ML20041G401 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/18/1982 |
| From: | Caruso R Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-03-07.D, TASK-3-7.D, TASK-RR LSO5-82-03-083, LSO5-82-3-83, NUDOCS 8203220210 | |
| Download: ML20041G401 (4) | |
Text
March 18, 1982 Docket No. 50-29
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Q Mr. James A. Kay 2
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Dear Mr. Kay:
SUBJECT:
SEP TOPIC III-7.D - CONTAINMENT STRUCTURAL INTEGRITY. TESTING YANKEE NUCLEAR POWER STATION Enclosed is our final evaluation of SEP Topic III-7.D.
This evaluation compares your facility, as described in your Safety Analysis Report dated November 18, 1981, and other information available ca Docket 50-29, with criteria used in licensing new facilities.
The evaluation concludes that the structural integrity test performed at Yankee is satisfactory when compared to current criteria.
This evaluation will be a basic input to the integrated safety assessment for your facility and may be changed in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.
Sincerely, Ralph Caruso, Project Manager Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
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OFFiClAL RECORD COPY uscro: m-ns+o nne ronu sia om NHCM 030 l
YANKEE Docket No. 50-29 Mr. Janes A. Kay cc Mr. James E. Tribble, President Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581 Greenfield Community College 1 College Drive Greenfield, Massachusetts 01301 Chai~rman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor One Ashburton Place Boston, Massachusetts 02108 V. S. Environmental Protection Agency Region 1 Office ATTN: EIS COORDINATOR JFK Federal Building Boston, Massachusetts 02203 Resident Inspector
. Yankee Rowe Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350 4
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SYSTEMATIC EVALUATION PROGRAM o
' TORIC III-7.D YANKEE NUCLEAR POWER STATION TOPIC:
III-7.0, Assessment of Containment Structural Integrity Test I.
INTRODUCTION The structural integrity test procedure and test results for the Yankee containment were evaluated against current criteria for such tests.
The purpose of the evaluation was to verify that the containment struc-tural in'tegrity test was in compliance with the current requirements of 10 CFR 50 and thus provide. assurance that the structure would perform its intended safety function.
II.
REVIEW CRITERIA
References:
A.
NRC Standard Review Plan Section 3.8.2 C.
ASME Boiler and Pressure Vessel Code,Section III, Division 1, Article NE-6000,1980 Edition D.
Yankee SAR for SEP Topic III-7.D References. A, B, and C outline current criteria for conducting and eval-uating contaimnent structural integrity tests. Reference D describes the containment tests actually conducted at the Yankee Nuclear Power Station.
III.
RELATED TOPICS AND INTERFACES SEP Topic VI-3, " Containment Pressure and Heat Removal Capability"- will provide an assessment of the adequacy of the original design pressure for the containment.
The evaluation described herein is based on the original design and test pressure loading of the containment as presented in reference D.
IV.
REVIEW GUIDELINES' The test procedure and results were compared with current NRC criteria for such tests in order to determine if any significant deviations existed.
An available portion of the Yankee Final Hazards Summary Report (FHSR) was also studied for background information.
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V.
EVALUATION The Yankee containment is a column-supported steel sphere (125 feet diame-ter) which was designed, fabricated, tested, and code stamped in accordance with the rules of the ASME Boiler and PPessure Vessel Code. The test pres-sure was 40 psig, which is 1.25 times design pressure, according to the information contained in reference D.
Current requirements indicate that the test pressure would be 1.1 times design (35.2 psig), thus the test pressure was quite conservative ~by today's standards.
According to the Yankee FHSR, the pressure was slowly raised to 20 psig and then raised by 4 psig increments to 40 psig. This pressure was held for a minimum of one hour and then reduced to 31.5 psig and bubble tested.
Current criteria requires gradually applying the pressure to not more than one half of test pressure and then increased in steps of approximately one tenth of test pressure until test pressure is reached.
Current. criteria then requires holding the test pressure for a minimum of 10 minutes and then reducing it to the greater of the design pressure or.75 times test pressure and examining.the vessel.
The test proce. dure used at Yankee is conservative when compared to current criteria.
The vessel is code stamped and thus it can be inferred that a qualified ASME inspector was present during the test-inge VI.
CONCLUSION Based on the review of the original structural integrity test in comparison to current test requirements, it is considered that the test was satisfactory and thus demonstrated that the structure is capable of performing its inten-ded safety function.
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