ML20041G377

Forwards Final Evaluation of SEP Topic III-7.D Re Containment Structural Integrity Test

ML20041G377
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/17/1982
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TASK-03-07.D, TASK-3-7.D, TASK-RR LSO5-82-03-080, LSO5-82-3-80, NUDOCS 8203220161
Download: ML20041G377 (6)

Text

.

(" 1 f

March 17,1982 Docket No. 50-155 a2 LS05-82-03-080 4

4 f

RGcs.y, DR g b h Mr. David J. VandeWalle J

- CA:gr%(?"%r Nuclear Licensing Administrator

'N c Consumers Power Company C.

W

/

1945 W. Parnall Road Jackson, Michigan 49201 6 4.

e

SUBJECT:

SYSTEMATIC EVALUATION PROGRAM TOPIC III-7.D. CONTAINMENT STRUCTURAL INTEGRITY TEST - BIG ROCK POINT Enclosed is a copy of our final evaluation of SEP Topic III-7.D.

This evaluation compares your facility as described in the Safety Analysis Report you supplied on December 29, 1981, and other information on Docket No. 50-155 with criteria currently used by the staff for licen-sing new facilities.

The evaluation concludes that the structural in-tegrity test performed compares favorably with current criteria.

This evaluation will be a basic input to the integrated assessment of your facility. This topic assessment may be changed in the future if your facility design is changed or if NRC criteria relating to this topic is modified before the integrated assessment is completed.

Sincerely, i

Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing i

Enclosure:

^

As stated i

cc w/ enclosure:

h*

See next page sy, l

g r888 r a888 m mum 4@)

du%

o,,,c,, "SEPB QY SEPB Y ORB #5

'0RB 65. a

@[SEPB,Pss1iT.~.

9.!M2e MMF9.~.E d.~SA D AD: ""7 EB".i.nW.9. bas ~.

~~

l k

. 3LI.1.6.?.........?.l.:::.l.82....... 3Idl.8L.

.. 3L!2M.....

..at lSt..

. 31f().62....

l omy 2

NRC FORM 318 (10 f,..nCM 024o OFF1CIAL RECORD COPY usem mi--sas.seo

Big Ru.A Point Docket Ns. 50-155 Reir. 2/8/82

~

Mr. David J. VandeWalle CC Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region Y Office ATTN:

Regional Radiation Representative Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Peter B. Bloch, Chairman Atomic Safety and Licensing Board

- Joseph Gallo, Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln & Beale Washington, D. C.

20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.

20036

. Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Peter W. Steketee, Esquire Washington, D. C.

20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. P,osenthal, Esq., Chairman-U. S. Nuclear Regulatory Commission Atomic Safety & Licensing Appeal Board Washington, D. 'C.

20555 U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Big Rock Point Nuclear Power Plant ATTN:

Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Haple City, Michigan 49664 Christa-Maria Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC Room 1 - Capttol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Semmel Mr. Jim E. Mills Counsel for Christa Maria, et al.-

Route 2, Box 108C Urban Law Institute Charlevoix, Michigan 49720 Antioch School of Law 263316th Street, NW Washington, D. C.

20460 e

2-Big Rock Point Docket No, 50-155 Mr. David J. VandeWalle cc Dr. John H. Buck

' Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 i

Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49720 Thomas S. Moore Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 James G. Keppler, Regional Administrator Nuclee Regulatory Commission, Region III Office of Inspection and Enforcement 799' Roosevelt Road Glen Ellyn, Illinois 60137 e

6 e

e e

9 e

e 9

4 e

~

ENCLOSURE BIG ROCK POINT PLANT DOCKET NO. 50-155 SEP TOPIC III-7.D.

ASSESSMENT OF CONTAINMENT STRUCTURAL INTEGRITY TEST

1. 0 INTRODUCTION The structural integrity test procedure and test results for the Big Rock Point containment were compared with current crit'eria 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 and thus provide assurance that the structure will continue to perform its intended safety function.

2.0 REVIEW CRITERIA

References:

(A) 10 CFR 50, Appendix A (B) HRC Standard Review Plant Section 3.8.2 (C) ASME Boiler and Pressure Vessel Code,Section III, Division 1, Article NE-6000,1980 Edition.

(D)

Letter from Consumers Power Co. to NRC, dated Decemb,er 29, 1981 with attachments.

References A, B and C outline current criteria for conducting and evaluating containment structural integrity tests.

Reference D describes the containment tests actually conducted at the Big Rock Point plant.

1

3.0 RELATED TOPICS AND INTERFACES SEP Topic VI-3, " Containment Pressure and Heat Removal Capability" will provide an a'sses' ment of the adequacy of the original design pressure for the s

containment.

The evaluation described herein is based on the design and test pressure loading of the containment as presented in reference D.

5.0 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.

5.0 EVALUATION The Big Rock Point containment is a steel sphere,130 feet in diameter and 3/4 inches thick.

The sphere extends 27 fee,t below grade and 103 feet above grade.

The containment was designed, constructed, and code stamped in accordance with the ASME Boiler and Pressure Vessel (B&PV) Code.

The material.

of the containment was SA-201, Grade B steel produced to specification SA-300.

The containment was to be subjected to a test pressure of 33,75 psig.

However, due to inadequacies in the instrumentation, itwas estimated that the actual test pressure was 31.75 psig.

Since the design pressure was 27 psig.

the test pressure was actually 31.75/27 = 1.176 times design.

This compares favorably with the current ASME-B&PV Code requirement for a test pressure of 1.1 times design'.

The test procedure and field log were compared with the current criteria per Article NE-6000 of Subsection NE of the ASME B&PV Code,Section III, Division 1.

The following deviations have been identified:

(1) The pressure gages used (2 indicating gages and 1 recording gage) were not calibrated.

The recording gage seemed to have overestimated by approximately 2 psig at the low ranDe.

As noted above, the test pressure actually used is conservative.

2

(2) The inner door pressure equalizing valves on both the personnel and equipment lock were not operating properly during the test.

The test was performed with these fully open.

This, however, does not invalidate the I

test.

Calculations submitted by the licensee for the design of the doors were examined and found to show conservative stress levels.

CONCLUSI0f]

Based on the review and the evaluation stated above, we conclude that the test procedure used was adequat'e and the test results. provide assurance that the containment structure will safely perform its intended functions.

O e

• *s M e

9 4

e 3

.