ML17194A606
| ML17194A606 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/13/1982 |
| From: | Oconnor P Office of Nuclear Reactor Regulation |
| To: | Delgeorge L COMMONWEALTH EDISON CO. |
| References | |
| TASK-03-07.D, TASK-3-7.D, TASK-RR LSO5-82-04-035, LSO5-82-4-35, NUDOCS 8204160530 | |
| Download: ML17194A606 (5) | |
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Dock et.No. 50-237 LS05 04- 03 5 Mr. L. DelGeorge 01rector of Nuclear Licensing Corrmonwealth Edison Company Post Office B-ox 767 Chicago, Illinois 60690 Dear Mr.
DelGeorge~
Apri 1 13, 1 982
SUBJECT:
SEP TOPIC III-7.D, CONTAIN~£NT STRUCTURAL INTEGRITY TEST DRESDEN NUCLEAR POWER STAlION UNIT 2 Enclosed is a copy of our final evaluation of SEP Topic 111-7.D. This evaluation compares your facility as described in the Safety Analysis Report you supplied on April 27, 1981 and other information on Docket No. 50-237 \\llith criteria used by the staff for licensing new facilities.
The evaluation concludes that the structural integrity test performed
- Corrµares favorably w1th current criteria.
This evaluation will be a basic input to the integrated assessment of your facility and may be changed in the future if your fac1.lity design is changed or if NRC criteria relating to this topic is modified before the integrated assessment 1s completed.
Enclosure:
As stated
. cc w/enclosure:
See next page Sincerely, P-aul O'Conn-or, Project Manager Operating Reactors Branch No. 5 Division of Licensing 1>.<..tJ. ll sE { l!)
JJ" NRCFORM318(10-80)NRCM0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
'\\
Mr. L. DelGeorge cc Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr. B. B. Stephenson Plant Superintendent Dresden Nuclear Power Station Rural Route #1 Morris, Illinois 60450
- The Honorable Tom Corcoran United States House of Represent"atives Washington, D. c.
20515
- u *. S. ~Juclear Regulatory Commission Resident Inspectors Office Dresden Station RR #1 Morris, Illinois 60450 Mary Jo Murray
\\ssistant Attorney General Environmental Control Division 188 W. Randolph Street Suite 2315 Chicago, Illinois 60601 Chairman Board of Supervisors of cGrundy County Grunay *tounty Courthouse Morris, Illinois 60450 John F. Wolf, Esquire 3409 Shepherd Street Chevy Chase, Maryland 20015 Dr. Linda W. Little 500 Hermitage Drive Raleigh, North Carolina 27612 Judge Forrest J. Remick
.The Carriage House - Apartment 205 2201 L Street, N. W.
Washington, D. C.
20037 Dresden 2 Docket No.. 50-237 Revised 3/30/82 Illinois.Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:
Regional Radiation Representative 230 South Dearborn Street Chicago, Illinois 60604 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Street Glen Ellyn, Illinois 60137
ENCLOSURE 1 DRESDEN STATION, UNIT 2 SEP TOPIC III-7.D ASSESSMENT OF CONTAINMENT STRUCTURAL INTEGRITY TEST I.
INTRODUCTION The structural integrity test procedure and test results for the Dresden, Unit 2 containment were evaluated in comparison to current criteria for such tests. The purpose of the evaluation was to verify that the containment structural integrity test was in compliance with the current requirements of 10 CFR 50 thus providing assurance that the structure will perform its intended safety function.
II.
REVIEW CRITERIA
References:
A.
B.
- c.
D.
E.
10 CFR 50, Appendix A ASME Boiler and Pressure Vessel Code,Section III, Division I, Subsection NE, Article NE6000, 1980 edition.
NRC Standard Review Plan Section 3.8.2 Dresden 2 SAR for SEP Topic III-7.D forwarded to NRC staff, Apri 1 27, 1981.
Original Test Report for Dresden 2, forwarded to NRC staff August 5, 1980.
References A, B, and C outline current criteria for conducting and evaluating containment structura~ integrity tests. References D and E describe the tests actually conducted at the Dresden 2 plant.,
J
- 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 this containmen:. The evaluation described herein is based on the original design and test pressure loading for the con-tainment as described in references D and E.
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.
V.
EVALUATION
.The Mark I containment vessel of the Dresden Station Unit 2 is a Class B vessel which was designed, fabricated, inspected, and N-stamped in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section III, 1965 Edition including the Summer 1965 Addend~. The c0ntainment vessel con$ists of a drywell, sup-pression chamber, and interconnecting vent system.
The containment was constructed of SA212, Grade B Firebox quality steel. This material specification no longer exists and has since been replaced by SA516, Grade 70, Carbon steel.
The design of the containment was based on the following material properties:
Ultimate strength = 70 ksi Yield strength
= 38 ksi The stress allowables are based on the requirements of the ASME Code,Section III, Article 13, 1965 Edition.
a
.;t)
- A pneumatic test was conducted at a maximum pressure of 71.3 psig which is 1. 15 times the design pressure of 62 psi. For this test, the suppr~ssion chamber was filled with water up to.mid-height.
The maximum pressure was held for one hour *. Based on a recent re-view, it has been determined that the structural integrity test was conducted in ~ccordance with the requirements of:
ASME Boi.ler and Pressure Vessel Code,Section III, Subsection.B, 1965 Edition including the Surmier 1965
- Addenda,
, the s*argent & Lundy Specification ~-2152, and the constructor!s *{Chicago Bridge & Iron) design criteria.
Th~ test ~as_~ertified On the N-1 Form, {manufa~turer~s data report for nuclear vessels) by the* authorized inspector, and included in the Dresden Units 2 & 3 FSAR; Appendix C.
In acc?r9ance with ASME Sedion III, Division 1, Article NE-6000, 1980 Edition including Winter 1980 Addenda~ the minimum required pneumatic test pressure is 1.10 times the de~ign pressu~e of the vessel. If applied to the Dresden Station Unit 2 containment, the te~t pressure w9uld be 68.2 psig which is les*s than what the con-tainment vessel was tested for originally.
The stress allowables permitted for the structural integrity pressure test load* case, in accordance with 'the current NRC acceptance criteria and the present ASME Boiler and Pressure Vessel Code, are higher than that permitted by the original construction specifications.
VI.
CONCLUSIONS Based on the review of the original structural integrity test {as outlined above) in comparison with current test criteria it is con-sidered that the test was satisfactory and thus demonstrated that the structure is capable of performing its intended safety function.