ML17258B141

Forwards Draft Evaluation of SEP Topic III-7.C Re Delamination of Prestressed Concrete Containment Structures. Requests Response within 30 Days of Receipt of Ltr

ML17258B141
Person / Time
Site:	Ginna
Issue date:	06/24/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Maier J ROCHESTER GAS & ELECTRIC CORP.
References
TASK-03-07.C, TASK-3-7.C, TASK-RR LSO5-81-06-093, LSO5-81-6-93, NUDOCS 8106290322
Download: ML17258B141 (6)

Text

June 24, 1981 Docket No. 50-244 LS05-81<<06-080 Mr. John E. Maier Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649

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SUBJECT:

SYSTEMATIC EVALUATION PROGRAM TOPIC III-7.C, DELAMINATION OF PRESTRESSED CONCRETE CONTAINMENT STRUCTURES - GINNA Enclosed is a copy of our draft evaluation of Systematic Evaluation Program Topic III-7.C.

You are requested to examine the facts upon which the staff has based its evaluation and respond either by confirming that the facts are correct, or by identifying errors and supplying the corrected information.

We encourage you to supply any other material that might affect the staff's evaluation of this topic or be significant in the integrated assessment of your facility.

Your response is requested within 30 days of receipt of this letter. If no response is received within that time, we will assume that you have no comments or corrections.

ln future correspondence regarding Systematic Evaluation Program topics, please refer to the topic numbers in your cover letter.

Sincerely, If

Enclosure:

Sl<62$ b~~~

cc w/enclosure:

See next page Dennis M. Crutchfield, Chief Operating Reactors Branch.No.

5 Division of Licensing OFFICE/

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Docket No. 50-244 LS05 06-093 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 24, 1981 Mr. John E. Maier Vice President Electric and Steam Production Rochester Gas

& Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

SYSTEMATIC EVALUATION PROGRAM TOPIC III-7.C, DELAMINATION OF PRESTRESSED CONCRETE CONTAINMENT STRUCTURES - GINNA Enclosed is a copy of our draft evaluation of Systematic Evaluation Program Topic III-7.C.

t You are requested to examine the facts upon which the staff has based its evaluation and respond either by confirming that the facts are correct, or by identifying errors and supplying the corrected information.

Me encourage you to supply any other material that might affect the staff's evaluation of this topic or be significant in the integrated assessment of your facility.

Your response is requested within 30 days of receipt of this letter..

If ao response is.received within that time, we will assume that you have no comments or corrections.

In future correspondence regarding Systematic Evaluation Program topics, please refer to the topic numbers in your cover letter.

Sincerely,

Enclosure:

As stated ennis M. Crutch gael ief Operating Reactors Branch No.

5 Division of Licensing cc w/enclosure:

See next page

~

~ ~

Yir. John E. Maier CC Harry H. Voigt, Esquire

LeBoeuf, Lamb, Leiby and NacRae 1333 New Hampshire

Avenue, N.

W.

Suite 1100 Washington, D. C.

20036-Nr. tiichael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra:Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center-New York, New York 10047 Jeffrey Cohen New York State E ne rgy Office Swan Street Building Core 1,

Second Floor Empire State Plaza

Albany, New York=

12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontari o 107 Ridge Road West

Ontario, New York

. 14519 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)

U. S. Environmental Protection Agency Washington, D.

C.

20460 U. S. Environmental Protection Agency Region II Office ATTN:

E I S COORDINATOR 26 Federal Plaza New'York, New York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Cormnission Washington, D. C.

20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Cormnission Washington, D.

C.

20555 Dr.

Erxneth A. Luebke Atomic Safety and Licensing Board U.

S. Nuclear Regulatory Commission Washington, D. C.

20555 Nr.

Tnomas B. Cochran Natural Resources Defense Council, Inc.

1725 I Street, N.

W.

Suite 600-Washington, D.

C.

20006 Resident Inspector R. E. Ginna Plant c/o U.

S.

NRC 1503 Lake Road

Ontario, New York 14519

~

~

ENCLOSURE GINNA PLANT DOCKET NO. 50-244 SEP TOPIC III-7.C DELAMINATION OF PRESTRESSED CONCRETE CONTAINMENT STRUCTURE I.

INTRODUCTION Delaminations of concrete have occurred in the domes of two orestressed concrete contai nments, Crystal River and Turkey Point.

The safety objec-tive of this review is to assure that the containment will maintain its structural integrity in order that it may perform its intended safety function.

II.

REVIEW CRITERIA REFERENCES a.

SER Turkey Point No. 3, Docket No. 50-250 b.

Containment Dome Report, Turkey Point No. 3, dated

February, 1972.

c.

SER Crystal River No. 3; Docket No.

50-302 d.

Reactor Building Dome Delamination Final Report, Crystal River No.

3 dated December 10, 1976.

Problem history, analyses and repair procedures are described in the above references for the plants where dome delaminations occurred.

The containment at Ginna, as described in the FSAR was compared with the containments referenced above in order to determine if such a failure could occur at Ginna.

III.

RELATED SAFETY TOPICS AND INTERFACES l.

Containment structural integrity tests are reviewed under SEP Topic III-7.d.

2.

Containment tendon inservice inspection program is reviewed under SEP Topic III-7.A.

IV.

REVIEW GUIDELINES The containment design and configuration are reviewed in order to assess the possibility that delamination might occur.

Recommendations, based on that assessment are noted below.

V.

EVALUATION Delamination (cracks in planes parallel to inner and outer concrete surfaces) is caused by radial tension developed in the concrete by the forces from curved prestressing tendons.

The curved prestressing tendons attempt to relieve the stresses in them and as a result may cause the concrete delaminate.

It appears that the two most significant factors which led to the

, delamination of the Turkey Point

-.,3 and Cr'ystal River

-",'.3 domes were radial tension in the concrete above the prestressing tendons and the use of a marginal strength coarse aggregate in the concrete.

The containment at Ginna is substantially different from Turkey Point

=:.'3 and Crystal River

-'.,'3 in that the Ginna containment only contains straight, vertical.prestressing tendons in the containment wall.

There is no prestressing in the hoop direction of the containment wall or in the dome.

Since there is no curvature in the prestressing tendons at Ginna, there would be no mechanism to cause radial tension in the concrete due to orestressing forces.

VI.

CONCLUSION The containment at Gi nna would not experience delamination because the containment has no curved prestressing tendons to cause radial tension and delamination in the concrete due to prestressing forces.