Information Notice 1998-13, Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality

From kanterella
Jump to navigation Jump to search
Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality
ML031050237
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: 04/20/1998
From: Roe J
Office of Nuclear Reactor Regulation
To:
References
IN-98-013, NUDOCS 9804150187
Download: ML031050237 (10)


05-9

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001

April 20, 1998

NRC INFORMATION NOTICE 98-13: POST-REFUELING OUTAGE REACTOR PRESSURE

VESSEL LEAK TESTING BEFORE CORE CRITICALITY

Addressees

All holders of operating licenses for nuclear power reactors except those that have permanently

ceased operations and have certified that fuel has been permanently removed from the reactor

vessel.

Purpose

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

addressees of the requirement to complete pressure tests and leak tests of the reactor

pressure vessel (RPV) before core criticality. 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.

Background

Under the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME

Code) , Section Xl, Class 1 and 2 leakage tests provide a level of defense-in-depth for detecting

pressure boundary leakage. From a safety perspective, performing this test using nuclear heat

defeats the intended purpose of ensuring the integrity of the RPV as a fission product barrier.

A December 1995 rule change to Part 50 of Title 10 of the Code of Federal Regulations

(10 CFFtlParts50), Appendix G,Section IV.A.2.d, clarified the staff position as follows:

"Pressure tests and leak tests of the reactor vessel that are required by Section Xi of the ASME

Code must be completed before the core is critical' The final rule was published in the Federal

Register on December 19, 1995. In addition, the Federal Register notice referenced a letter to

Messrs. Reynolds and Stenger of the Nuclear Utility Backfitting and Reform Group (NUBARG)

from James M. Taylor, NRC Executive Director for Operations, dated February 2, 1990, in

which Mr. Taylor discussed the explicit prohibition of using nuclear heat to perform pressure

and leak tests (Accession Number 9002120362).

6

~

?D

Aft

E £ODT[69-0131 Rso0

IN 98-13 April 20, 1998

Description of Circumstances

On June 22, 1997, the licensee for Quad Cities Station performed the required ASME Code, Section Xl leak test of the RPV following Unit 2 criticality and startup from a refueling outage.

The reactor was at approximately 12-percent power. On October 1, 1997, while reading

Appendix G for guidance on a separate issue, the licensee discovered that it had violated the

requirement to complete pressure and leak testing before the core is taken critical.

In December 1997, a Region IlIl inspector reviewed (1) ASME Code Class I system pressure

tests for the Quad Cities Units 1 and 2 refueling outage 14 and (2) problem identification

forms (Inspection Report 50-254/97-27, Accession Number 9803170418). The licensee had

previously documented the violation that took place on June 22, 1997, of Appendix G

requirements in one of the problem identification reports. The Inspector found that the visual

VT-2 examinations of the Unit 2 drywell area required by the ASME Code were conducted in a

very short time. In an effort to keep exposure time to a minimum, licensee personnel covered

very large examination areas in a very short time (e.g., 50 examination areas in 12 minutes).

The short examination time called into question the adequacy of the visual VT-2 examinations.

The NRC and the licensee discussed apparent violations during an open, predecisional

enforcement conference that took place on January 9, 1998. On March 12, 1998, the NRC

issued a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $330,000

for violations of Appendix G to 10 CFR Part 50, 10 CFR 50.59, and Technical Specification

surveillance requirements.

Discussion

This issue is of significant concern because licensees should recognize that the intent of

performing the ASME Code pressure and leak tests before the reactor is taken critical is to

ensure the integrity of the RPV without using nuclear heat. The staffs position has been, and

continues to be, that performing pressure and leak tests after the core is critical is

unacceptable. This point was clarified in the December 1995 rule change.

4

K>

IN 98-13 April 20, 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) when practical and when setting goals and performing periodic evaluations

under 10 CFR Section 50.65, "Requirement 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:

Andrea D. Lee, NRR

301-415-2735 E-mail: adwl

nrc.gov

Melvin Holmberg, Rill

630-829-9748 E-mail: mshenrc.gov

Attachment: List of Recently Issued NRC Information Notices

Tech Editor had concurred on 3118198

1 J

(

DOCUMENT NAME: G:NVERN\\CRITLEAK.IN

  • See Previous Concurrence

INDICATE IN BOX: "C"=COPY W/O ATTACHMENTIENCLOSURE, "E"COPY WIATI

"N"NO COPY

I

Attachment

IN 98-13

April 20, 1998

Page 1 of I

LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issuance

Issued to

98-12 Licensees' Responsibilities

4/3198

All U.S. Nuclear Regulatory

Regarding Reporting and Follow-up

Requirements for Nuclear-Powered

Pacemakers

Commission nuclear pacemaker

licensees

98-11

Cracking of Reactor Vessel

Internal Baffle Former Bolts

in Foreign Plants

3/25/98

All holders of operating licensing

for pressurized-water reactors

(PWRs) except those who have

ceased operation and have

certified that fuel has been

permanently removed from the

reactor vessel.

95-52, Supp.1

Fire Endurance Test Results

for Electrical Raceway Fire

Barrier Systems Constructed

From 3M Company Interam

Fire Barrier Materials

3/17/98

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.

98-10

98-09

98-08

Probable Misadministrations

Occurring During Intravascular

Brachytherapy With The

Novoste Beta-Cath System

Collapse Of An Isocam II

Dual-Headed Nuclear

Medicne Gamma Camera

Information Likely To Be

Requested If An

Emergency Is Declared

Offsite Power Reliability

Challenges from Industry

Deregulation

3/9198

315/98

3/2/98

2/27/98

All Medical Licensees

All Medical Licensees

All Parts 30,40, 70, 72, and

76 licensees and certificate

holders required to have a

Nuclear Regulatory Commission- approved Emergency Plan.

All holders of operating licensees

for nuclear power reactors

98-07 OL = Operating License

CP = Construction Permit

I

IN 98-13 April 20, 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) when practical and when setting goals and performing periodic evaluations

under 10 CFR Section 50.65, "Requirement 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:

Andrea D. Lee, NRR

301-415-2735 E-mail: adwl@nrc.gov

Melvin Holmberg, Rill

630-829-9748 E-mail: msh@nrc.gov

Attachment: Ust of Recently Issued NRC Information Notices

Tech Editor had concurred on 3/18/98 DOCUMENT NAME: G:\\VERN\\CRITLEAK.IN

  • See Previous Concurrence

N DICATE IN BOX: "C"=COPY WIO ATTACHMENTIENCLOSURE, "E"=COPY WIATTIENCL, "N"=N0 COPY

OFFICE

EMCB:

E EMCB:DE

(A)D:DE

E

C:PECB

l

OE

(A)D:DRP il

NAME

ADLee

l klidhman

n

I GLainas*

SRichards

JLieberman*

JRoe*

ill

I,

DATE

IN 98-XX

Marchxx, 199

Page 3 of

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

er, recipients are

reminded that they are required to consider industry-wide operating ex

ence (including NRC

information notices) when practical and when setting goals and perfo

ing periodic evaluations

under 10 CFR Section 50.65, "Requirement for Monitoring the Effe iveness of Maintenance at

Nuclear Power Plants," If you have any questions about the inf

ation in this notice, please

contact one of the technical contacts listed below or the appr

riate Office of Nuclear Reactor

Regulation (NRR) project manager.

Jack

AV/koe, Acting Director

fn of Reactor Program Management

of Nuclear Reactor Regulation

Technical contacts:

Andrea D. Lee,

301-415-2735 E-mail: adw@i

Melvin

Attachment: List of

Issued NRC Information Notices

DOCUMENT

INDICATE IN BOX: "C"

OFFCE

MCB

Previous Concurrence

COPY

OFFICE

I EMCB:

DE

IN 98-XX

March 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) when practical and when setting goals and performing periodic evaluations

under 10 CFR Section 50.65, "Requirement 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:

Andrea D. Lee, NRR

301-415-2735 E-mail: adwl@nrc.gov

Melvin Holmberg, Rill

630-829-9748 E-mail: msh@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:%VERN\\CRITLEAK.IN

  • See Previous Concurrence

INDICATE IN BOX: "C"=COPY W/O ATTACHMENTIENCLOSURE, "E"=COPY WIATTIENCL, "N"N=

COPY

IOFFICE

EMCB:DE

l

DDET E

C

J

(A)D:DRPM

NAE

ADLee*

KWichman

v

GLainas*

SRichards

JUeberman- JRoe

DATE

3 /3 /98

3/38

3/12/98

__8

3116/98

3/

/98

OFFICIAL RECORD COPY

IN 98-XX

March 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) when practical and when setting goals and performing periodic evaluations

under 10 CFR Section 50.65, "Requirement 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:

Andrea D. Lee, NRR

301-415-2735 E-mail: adwl@nrc.gov

Melvin Holmberg, Rill

630-829-9748 E-mail: msh@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\\VERN\\CRITLEAK.IN

See Previous Concurrence

INDICATE IN BOX: CCOPY W/O ATTACHMENTIENCLOSURE, 'ELECOPY WIATTIENCL, 'NNO COPY

OFFICE

EMCB:DE I E EMCB:DE

(A)D:DE I E

C:PECB

D:OE

(A)D:DRPM

NAME

ADLee*

KWIchman *

GLainas*

SRichards

JUeberman

JRoe

DATE

3 /3 /98

13//98

3112 /98

31 /98

13/16198

31 _98

OFFICIAL RECORD COPY

IN 9X-XX

Month XX, 199X

Page X of X

power plants," to Part 50 of Title 10 of the Code of Federal Regulations.) If you have any

questions about the Information in this notice, please contact the technical contact 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 contact(s): Andrea D. Lee, NRR

(301) 415-2735 E-mail: adwl@nrc.gov

Melvin Holmberg, Rill

(630) 829-9748 E-mail: msh@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

DISTRIBUTION

PUBLIC

EMCB RFIPF

File Center

MHolmberg, Rill

MMayfield (RES)

DOCUMENT NAME: G:\\LEE\\QUAD IN2.WPD

See Previous Congurrence

IaIfmclms

W Nfy.

ROX

dlVPY Win ATTACHMUElTENCLOSURE. SE-COPY WIATThENCL

NN".NO COPW

OFFICE

EICB:DEV E EMCB:DE

IE

(A

DE

D:

D:PECB

NAME

ADLee

KWchiman

as

Jeberman

JRoe

DATE

3 /3 /98

3 /3/8418<t

/98

/98 OFFICIAL RECORD COPY

-

IN 9X-XX

Month XX, 199X

Page X of X

In addition, there was a lack of knowledge of the change in the applicable regulation.Which

suggests a weakness in the method for disseminating rule changes to the onsite

if. This

raises a larger concern with regard to how licensees with multiple sites ensureiat their sites

receive information each time a rule is changed. It should also be noted that

o formal onsite

staff review occurred prior to the decision to perform the pressure test afte criticality.

This informatiqn notice requires no specific action or written response

owever, recipients are

reminded that t1ey are required to consider industry-wide operating

perience (including NRC

information notices) where practical, when setting goals and perfo

ing periodic evaluations

under Section 50.65, "Requirement for monitoring the effectivenss of maintenance at nuclear

power plants," to Part 50 of Title 10 of the Code of Fed

.

..) If you have any

questions about the inkormation in this notice, please conta

e technical contact listed below

or the appropriate Offi&,of Nuclear Reactor Regulation (N

) project manager.

Jack

.Roe, Acting Director

Diviin of Reactor Program Management

ce of Nuclear Reactor Regulation

Technical contact(s): Andrea D. Lee,

(301) 415-2735 E-mail: adwi

r

Melvin Hol6 b

(630) 8

9748 E-ma mshenr

Attachment: List of ecentlv Issued NIRC Information

MMayfield (RES)

File Center

DOCUMENT NAME: G:\\LEE\\QUAD N2.WPD

/*

INDICATE IN BOX:L 'CCOPY W10 ArTACHMENTIE

LOSURE. -E".COPY WiATTAENcL -NuNo COPY

OFFICE

EMCB:DE

E:t B

_J

l (A)D:DE

I

D:OE ZZ

D:PECB

I

NAME

l ADLeKS

7i

GLainas

JUeberman

JRoe

DATE

13 /3/98 J5t

/98

1 198l

I

/98

OFFICIAL RECORD COPY

f V