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

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, 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:	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).

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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

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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

"N"NO COPY

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

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 Commission nuclear pacemaker

Requirements for Nuclear-Powered licensees

Pacemakers

98-11 Cracking of Reactor Vessel 3/25/98 All holders of operating licensing

Internal Baffle Former Bolts for pressurized-water reactors

in Foreign Plants (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 3/17/98 All holders of operating

for Electrical Raceway Fire licenses for nuclear power

Barrier Systems Constructed reactors except those who

From 3M Company Interam have permanently ceased

Fire Barrier Materials operation and have certified that

fuel has been permanently

removed from the reactor vessel.

98-10 Probable Misadministrations 3/9198 All Medical Licensees

Occurring During Intravascular

Brachytherapy With The

Novoste Beta-Cath System

98-09 Collapse Of An Isocam II 315/98 All Medical Licensees

Dual-Headed Nuclear

Medicne Gamma Camera

98-08 Information Likely To Be 3/2/98 All Parts 30,40, 70, 72, and

Requested If An 76 licensees and certificate

Emergency Is Declared holders required to have a

Nuclear Regulatory Commission- approved Emergency Plan.

98-07 Offsite Power Reliability 2/27/98 All holders of operating licensees

Challenges from Industry for nuclear power reactors

Deregulation

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

I,NDICATE 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 klidhmann I GLainas* SRichards JLieberman* JRoe* ill

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 Previous Concurrence

INDICATE IN BOX: "C" COPY

OFFCE MCB

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

IOFFICE

DOCUMENT NAME: G:%VERN\CRITLEAK.IN *See Previous Concurrence

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

EMCB:DE l DDETE 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 MMayfield (RES)

File Center MHolmberg, Rill

DOCUMENT NAME: G:\LEE\QUAD IN2.WPD See Previous Congurrence

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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:OEZZ D:PECB I

NAME l ADLeKS 7i GLainas JUeberman JRoe

DATE 13 /3/98 J5t /98 1 198l I /98 OFFICIAL RECORD COPY

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