Information Notice 1998-26, Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations

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Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations
ML031050126
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  Entergy icon.png
Issue date: 07/24/1998
From: Roe J
Office of Nuclear Reactor Regulation
To:
References
IN-98-026, NUDOCS 9807200110
Download: ML031050126 (11)


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UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001

July 24, 1998

NRC INFORMATION NOTICE 98-26: SETTLEMENT MONITORING AND INSPECTION OF

PLANT STRUCTURES AFFECTED BY

DEGRADATION OF POROUS CONCRETE

SUBFOUNDATIONS

Addressees

All holders of operating licenses for nuclear power reactors; all holders of or applicants for

licenses to operate Independent Spent Fuel Storage Installations; and designers and

fabricators of Independent Spent Fuel Storage Installations.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform

addressees who own and operate facilities with plant sites that include structures with porous

concrete subfoundations of the possibility of degradation of these subfoundations. Such

degradation could have deleterious effects on structures, systems, and components (SSCs).

It Is expected that recipients will review the Information for applicability to their facilities and

consider actions, as appropriate, to avoid similar problems. However, suggestions contained in

this information notice are not NRC requirements; therefore, no specific action or written

response Is required.

Description of Circumstances

The containment structure at Millstone Nuclear Power Station, Unit 3 (MNPS-3), has a

3.05-meter (10-foot) thick reinforced-concrete basemat founded on rock. Between the

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foundation rock surface and the underside of the basemat are several layers of different

materials. These layers consist of (1) a 25.4-cm (1 -Inch) thick leveling layer of porous

concrete made of coarse aggregates and Portland cement, (2) a 0.16-cm (1/16th-inch) thick

butyl rubber waterproofing membrane, (3) a 5.08-cm (2-Inch) thick Portland cement mortar seal, IJ)

(4) a second layer of 22.86-cm (9-inch) thick porous concrete made of coarse aggregates and

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layer of the porous concrete. In the upper porous concrete layer, 15-cm (6-Inch) diameter

porous concrete pipes are Installed to collect and drain ground water, which may seep down

along the periphery of the containment wall. The collected water drains into two sumps inside

the engineered safety features (ESF) building.

The MNPS-3 licensee, Northeast Nuclear Energy Company, identified the Issue of cement

erosion from the porous concrete drainage system In 1987 upon examination of the

accumulated white residue In the two lower drain sumps In the ESF building. IN 97-11,

"Cement Erosion From Containment Subfoundations at Nuclear Power Plants," was Issued on

March 21, 1997, to alert addressees to the potential for erosion of cement from porous concrete

subfoundations.

The main concern raised by the cement erosion at MNPS-3 is the continued ability of the

degraded porous concrete subfoundations to transfer the loads of seismic Category I structures

to the underlying foundation medium without detrimental settlement. To address the question

of whether other nuclear power plant sites have this condition, the staff reviewed the updated

final safety analysis reports (UFSARs) of 24 plants selected on the basis of the unique practice

of the constructor or the architect/engineer (ANE) firm to use porous concrete subfoundations, and a sampling of other A/E firms. This limited-scope review revealed that at least 12 other

reactor units have porous concrete subfoundations (reference: IN 97-11). A survey of these

12 units indicated that the licensees of three units (i.e., Millstone 3, Nine Mile Point 2, and

Maine Yankee) have implemented surveillance programs to monitor for possible cement

erosion from the subfoundations beneath the containment basemats. In addition, the Perry

licensee has reported that dissolved calcium carbonate is being carried to the drainage pipes

and the sumps, where it is solidifying as a hard scale. The Perry licensee also discovered an

accumulation of mineral deposits that Is clogging the pores of the porous concrete pipes.

Although most of the surveyed licensees report that there is no evidence of cement erosion

from the porous concrete subfoundations, a review of their reports indicates that there is some

discharge of water (including some leachate) in several of the plants.

Discussion

Various types of porous concrete subfoundations may have been constructed at other plants.

The degradation of porous concrete leading to the creation of voids and local pockets of loose

concrete could eventually result In undesirable settlement of a structure. An effective way to

determine the presence of such effects is to Inspect and monitor seismic Category I structures

(that have porous concrete subfoundations) and the associated systems and components for

evidence of structural settlement

The settlement of a structure can give rise to a number of effects, some that are observable by

Inspection and some that are not so visible. If settlement Is uniform, that is, all parts of the

basemat settle an equal amount, the structure Itself may not show appreciable distress.

However, the alignments of the attached piping, electric cable lines, and Instrument lines would

be changed from their original, as-built configuration. If settlement is not uniform, the effects

could be visible on a concrete structure In the form of cracking near areas of stress

concentration, such as at discontinuities and large penetrations.

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\\JIN 98-26 July 24, 1998 The differential settlement could cause overstressing in a steel structure and could also affect

the alignment of, and stresses In, the attached piping, electric cable lines, and instrument lines.

Moreover, the differential settlement could cause misalignment of cranes and monorails. GDC 16 of Appendix A to 10 CFR Part 50 requires that "reactor containment and associated systems

shall be provided to establish an essentially leaktight barrier against the uncontrolled release of

radioactivity to the environment and to assure that the containment design conditions important

to safety are not exceeded for as long as postulated accident conditions require." GDC 55 (referring to reactor coolant pressure boundary penetrating containment) requires, In part, that

"other appropriate requirements to minimize the probability or consequences of an accidental

rupture of these lines or of lines connected to them shall be provided as necessary to assure

adequate safety." As explained In the preceding paragraphs, detrimental settlement as a result

of erosion of cement from the porous concrete subfoundation could result In overstressing of

the pipes (lines) penetrating the containment structure and Increase the probability of an

accidental rupture of these lines or of lines connected to them. Criterion XVI of Appendix B to

10 CFR Part 50 requires licensees to take appropriate corrective actions when conditions

adverse to quality and safety are detected. Detrimental settlement of a structure (for any

reason) can be characterized as a condition adverse to quality and safety.

Safety-related and certain non safety-related structures are required by the maintenance rule

(10 CFR 50.65) to be within the scope of the licensee's structural monitoring program.

NUMARC 93-011 provides guidelines to the industry for monitoring the effectiveness of

maintenance at nuclear power plants In accordance with the requirements of the maintenance

rule. NRC Regulatory Guide (RG) 1.160, Monitoring the Effectiveness of Maintenance at

Nuclear Power Plants," Revision 2, March 1997, endorses NUMARC 93-01, Revision 2.

Section C.1.5 of RG 1.160 describes the attributes of an acceptable structural monitoring

program for the purposes of complying with the maintenance rule and evaluating structural

degradation resulting from degraded conditions such as porous concrete erosion.

The NRC staff may Inspect licensees' subfoundation monitoring and preventive maintenance

programs as part of the NRC Inspection program as described In NRC Inspection Procedures

IP 62002 and IP 62003.

Related Generic Communications

IN 97-11, "Cement Erosion From Containment Subfoundations at Nuclear Power Plants, dated

March 21, 1997."

'NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at

Nuclear Power Plants," Revision 2, April 1996.

IN 98-26 July24, 1998 This information notice requires no specific action or written response. However, recipients are

reminded that they are required to consider Industry-wide operating experience (including NRC

information notices) where practical, when setting goals and performing periodic evaluations

under 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at

Nuclear Power Plants." If you have any questions about the Information in this notice, please

contact one of the technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Ja4e

. Roe, Acting Director

D

ion of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts:

R. Pichumani, NRR

H. Ashar, NRR

301-415-2734

301-415-2851 E-mail: rxp@nrc.gov

E-mail: hga~nrc.gov

W. Burton, NRR

301-415-2853 E-mail: wfb~nrc.gov

Attachment: List of Recently Issued NRC Information Notices

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Attachment

IN 98-26 -

July 24, 1998

Page 1 of I

LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issuance

Issued to

98-25 Loss of Inventory from Safety-

7/08198 Related, Closed-Loop Cooling

Water Systems

98-24

98-23

Stem Binding in Turbine

Govemor Valves In Reactor

Core Isolation Cooling (RCIC)

and Auxiliary Feedwater (AFW)

Systems

Crosby Relief Valve Setpoint

Drift Problems Caused by

Corrosion of the Guide Ring

Deficiencies Identified

During NRC Design

6/26/98

6/26/98

6123/98

All holders of OLs for nuclear

power reactors; except those

licensees who have permanently

ceased operations and have

certified that fuel has been

permanently removed from the

reactor vessel.

All holders of operating licenses

for nuclear power reactors except

those who have permanently

ceased operation and have

certified that fuel has been

permanently removed from the

reactor vessel

All holders of operating licenses

for pressurized water reactors

(PWRs), except those licensees

permanently ceased operations

and have certified that fuel has

been permanently removed from

the reactor vessel

All holders of operating licenses

for nuclear power reactors, except those licensees who have

permanently ceased operations

and have certified that fuel has

been permanently removed from

the reactor vessel

98-22 OL = Operating License

CP = Construction Permit

IN 98-26 July 24, 1998 This information notice requires no specific action or written response. However, recipients are

reminded that they are required to consider industry-wide operating experience (including NRC

information notices) where practical, when setting goals and performing periodic evaluations

under 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at

Nuclear Power Plants." If you have any questions about the information in this notice, please

contact one of the technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts:

R. Pichumani, NRR

301-415-2734 E-mail: rxp~nrc.gov

H. Ashar, NRR

301-415-2851 E-mail: hgainrc.gov

W. Burton, NRR

301-415-2853 E-mail: wfb@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

  • See previous concurrence

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reminded that they are required to consider industry-wide operating experience (including NRC

information notices) where practical, when setting goals and performing periodic evaluations

under 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at

Nuclear Power Plants." If you have any questions about the information in this notice, please

contact one of the technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts:

R. Pichumani, NRR

301-415-2734 E-mail: rxp@nrc.gov

H. Ashar, NRR

301-415-2851 E-mail: hga@nrc.gov

W. Burton, NRR

301-415-2853 E-mail: wfb@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

  • See previous concurrence

DOCUMENT NAME:

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reminded that they are required to consider industry-wide operating experience (including NRC

information notices) where practical, when setting goals and performing periodic evaluations

under 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at

Nuclear Power Plants." If you have any questions about the information in this notice, please

contact one of the technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts:

R. Pichumani, NRR

301-415-2734 E-mail: rxp@nrc.gov

H. Ashar, NRR

301-415-2851 E-mail: hga@nrc.gov

W. Burton, NRR

301415-2853 E-mail: wfb@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

  • See previous concurrence

DOCUMENT NAME:

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June xx, 1998 This information notice requires no specific action or written response. However, recipients are

reminded that they are required to consider industry-wide operating experience (including NRC

information notices) where practical, when setting goals and performing periodic evaluations

under 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at

Nuclear Power Plants." If you have any questions about the information in this notice, please

contact one of the technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts:

R. Pichumani, NRR

H. Ashar, NRR

301-415-2734

301-415-2851 E-mail: rxp@nrc.gov

E-mail: hga@nrc.gov

W. Burton, NRR

301-415-2853 E-mail: wfb@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

  • See previous concurrence

DOCUMENT NAME:

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performance or condition of all SSCs associated with storage, control, and maintenance of

spent fuel in a safe condition in a manner sufficient to provide reasonable assurance that such

SSCs are capable of fulfilling their intended functions.

Paragraph (a)(2) of 10 CFR 50.65 states that monitoring as specified in paragraph (a)(1) is not

required when it has been demonstrated that the performance or condition of an SSC is being

effectively controlled through the performance of appropriate preventive maintenance, such that

the SSC remains capable of performing its intended function. It is the staff's position that

monitoring for the subject condition and its associated effects as required by paragraph (a)(1)

or performance of appropriate preventive maintenance as required by paragraph (a)(2) is

appropriate and in keeping with NRC regulations. The NRC staff will inspect licensees'

subfoundation monitoring and preventive maintenance programs as part of its normal

maintenance rule inspection program.

Related Generic Communications

IN 97-11, 'Cement Erosion From Containment Subfoundations at Nuclear Power Plants, dated

March 21, 1997.'

This information notice requires no specific action or written response. However, recipients are

reminded that they are required to consider industry-wide operating experience (including NRC

information notices) where practical, when setting goals and performing periodic evaluations

under 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at

Nuclear Power Plants." If you have any questions about the information in this notice, please

contact one of the technical contacts listed below or the appropriate Office of Nuclear Reactor

Regulation (NRR) project manager.

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts:

R. Pichumani, NRR

H. Ashar, NRR

301-415-2734

301-415-2851 E-mail: rxp@nrc.gov

E-mail: hga@nrc.gov

W. Burton, NRR

301-415-2853 E-mail: wfb~nrc.gov

Attachment: List of Recently Issued NRC Information Notices

DOCUMENTNAME:

G:\\WFBUIN STRUC.WPD

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June xx, 1998 It is the staff's position that monitoring for the subject condition and its associated effects as

required by Paragraph (a)(1 or performance of appropriate preventive maintenance as required

by Paragraph (a)(2) is appropriate and in keeping with NRC regulations. The NRC staff will

inspect licensees' subfoundathpn monitoring and preventive maintenance programs as part of

its normal Maintenance Rule ir~ pection program.

Related Generic Communicatioi

Information Notice (IN) 97-11,"Ce

nt Erosion from Containment Subfoundations at Nuclear

Power Plants"

This information notice requires no spec c action or written response. However, recipients are

reminded that they are required to consid

industry-wide operating experience (including NRC

information notices) where practical, when etting goals and performing periodic evaluations

under Section 50.65, "Requirements for Mon oring the Effectiveness of Maintenance at Nuclear

Power Plants," to Part 50 of Title 10 of the Co

of Federal Regulations. If you have any

questions about the information in this notice, plase contact any of the technical contacts listed

below or the appropriate Office of Nuclear React

Regulation (NRR) project manager.

Jack W.oe, Acting Director

Division o

eactor Program Management

Office of N lear Reactor Regulation

Technical Contacts:

R. Pichumani, NRR

H. Ash , NRR

301-415-2734

301-415 851 E-mail: rxp@nrc.gov

E-mail: hg @nrc.gov

W. Burton, NRR

301-415-2853 E-mail: wfbenrc.gov

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