Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head

Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head

ML031140130
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, Three Mile Island, 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
Issue date:	05/03/1990
From:	Rossi C Office of Nuclear Reactor Regulation
To:
References
IN-90-032, NUDOCS 9005030007
Download: ML031140130 (5)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 May 3, 1990-

NRC INFORMATION NOTICE NO. 90-32: SURFACE CRACK AND SUBSURFACE INDICATIONS

IN THE WELD OF A REACTOR VESSEL HEAD

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

This information notice is intended to alert addressees to a potential problem

related to cracks found in the weld of a reactor vessel head. It Is expected

that recipients will review the information for applicability to their facili- ties and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice do not constitute NRC require- ments; therefore, no specific action or written response is required.

Description of Circumstances

In April 1990, while the James A. Fitzpatrick Nuclear Power Plant was shut down

for refueling, the licensee found a surface crack and some subsurface indications

in the reactor vessel head while performing routine inservice inspections. The

crack and subsurface indications are circumferentially oriented and located in

the weld that Joins the circular upper head portion (dollar plate) to the curved

trapezoidal portions (meridian plate) of the head. The dollar plate is located

at the top of the vessel head. The licensee observed a crack measuring 1 inch

long on the inside surface of the head and confirmed the observation by surface

examination. A group of 4 subsurface indications in the general area of the

surface crack has a length of 12 inches, and a maximum depth of 2 inches (50

percent through wall). The licensee found and measured subsurface indications

using ultrasonic examination methods. The licensee plans to take some metal- lurgical samples from the cracked area to determine the mode and mechanism of

the defects.

Discussion:

This is the second recent incident in which cracks have been observed in a

reactor vessel head. The first incident occurred at Quad Cities Station, Unit 2. As a result, on April 23, 1990, the General Electric Company issued

RICSIL No. 050, "Reactor Pressure Vessel Head Clad Cracking." On April 30,

the NRC issued Information Notice No. 90-29, "Cracking of Cladding and Its

9005030007 Z.

. 0

IN 90-32 May 3, 1990 Heat-Affected Zone in the Base Metal of a Reactor Vessel Head." These documents.

discussed the cracking of the stainless steel cladding and its heat-affected

zone in the base metal of the reactor vessel head at the Quad Cities facility.

However, at Fitzpatrick, the reactor vessel head has no cladding, and the crack

and subsurface indications are in the weld.

The information provided in this information notice is preliminary. When more

information becomes available, a supplement will be issued if appropriate.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate NRR project

manager.

aefs E. Rossi, D rdecto

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact WTIa Koo, NRRW-

msH.

(301) 492-0928 T. Greene, NRR

(301) 492-1176 Attachment: List of Recently Issued NRC Information Notices

- I

Attachment

IN 90-32 May 3, 1990 LIST OF RECENTLY ISSUED ' ' " ~, i

. I

'NRC INFORMATION NOTICES I

. . . . '. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Information Date of

Notice No.. Subject.Issuance Issuedto.......................

90-31 Update on Waste Form and '5/4/90 'All holders of'OLs

High Integrity Container or CPs for nuclear

Topical Report Review. power reactors, fuel

Status, Identification ... cycle lieensesi and L

of Problems with Cement certain by-product

Solidification, and . materials licenses.

Reporting of Waste Mishaps

90-30 Ultrasonic Inspection 5/1/90 All holders of OLs

Techniques for Dissimilar or CPs for nuclear

Metal Welds power reactors.

90-29 Cracking of"Cladding and 4/30/90 All holders of OLs

Its Heat-Affected Zone in or CPs for nuclear

the Base Metal of a Reactor power reactors.

_Vessel Head _

. 43/ i, - - . ,_ _ . _

90-28 Potential Error in High 4/30/90 iAll holders of OLs

Steamline Flow Setpoint or CPs for BWRs.

90-27 Clarification of the 4/30/90 All uranium fuel

Recent Revisions to the fabrication and

Regulatory Requirements conversion facilities.",

for Packaging of Uranium

Hexafluoride (UF6 ) for

Transportation

89-70, Possible Indications of 4/26/90 All holders of OLs

Supp. 1 Misrepresented Vendor or CPs for nuclear

Products power reactors.

90-26 Inadequate Flow of 4/24/90 All holders of OLs

Essential Service Water or CPs for nuclear

to Room Coolers and Heat power reactors.

Exchangers for Engineered

Safety-Feature Systems

90-25 Loss of Vital AC Power 4/16/90 All holders of OLs

with Subsequent Reactor or CPs for nuclear

Coolant System Heat-Up power reactors.

OL = Operating License

CP - Construction Permit

IN 90-32 May 3, 1990 Heat-Affected Zone in the Base Metal of a Reactor Vessel Head." These documents

discussed the cracking of the stainless steel cladding and its heat-affected

zone in the base metal of the reactor vessel head at the Quad Cities facility.

However, at Fitzpatrick, the reactor vessel head has no cladding, and the crack

and subsurface indications are in the weld.

The information provided in this information notice is preliminary. When more

information becomes available, a supplement will be issued if appropriate.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate NRR project

manager.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: William H. Koo, NRR

(301) 492-0928 T. Greene, NRR

(301) 492-1176 Attachment: List of Recently Issued NRC Information Notices

• SEE PREVIOUS PAGE FOR CONCURENCES

• EAB:DOEA:NRR *TECH ED *AC:EAB:DOEA *EMCB:DET *C:EMCB:DET

TGreene JMain PBaranowsky EKoo CYCheng

5/2/90 5/2/90 5/2/90 5/2/90 5/2/90

• D:DET:NRR *C:OGCB:DOEA

JRichardson CHBerlinger

5/2/90 5/2/90 5/_3 /90

Document Name: IN 90-32

IN 90-32 May xx, 1990 Zone in the Base Metal of a Reactor Vessel Head." These documents discussed

the cracking of the stainless steel cladding and its heat-affected zone in the

base metal of the reactor vessel head at the Quad Cities facility. However, at Fitzpatrick, the reactor vessel head has no cladding, and the crack and

subsurface indications are in the weld.

The information provided in this information notice is preliminary. When more

information becomes available, a supplement may be issued if appropriate.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate NRR project

manager.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contacts: William H. Koo, NRR

(301) 492-0928 T. Greene, NRR

(301) 492-1176 Attachment: List of Recently Issued NRC Information Notices

EAB:DOEA:NRR TECH ED AC:E

TGreene B PBar nowsky E5o/A9T CYCheng

5/ -Z/90f7 5/ 7 / 0 5/ /90 5/ Q /90 5/8- /90

D:DET: NR C:4? D:DOEA:NRR

JRichards CHBerlinger CERossi

5/ >,/90 5/ 90 5/ /90

Document Name: IN 90-32