Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor

Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor

ML031060172
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:	10/06/1995
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
References
IN-95-046, NUDOCS 9509280321
Download: ML031060172 (9)

K> I

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 October 6, 1995 NRC INFORMATION NOTICE 95-46: UNPLANNED, UNDETECTED RELEASE OF RADIOACTIVITY

FROM THE EXHAUST VENTILATION SYSTEM OF A

BOILING WATER REACTOR

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information material, notice to inform addressees of an undetected release of radioactive is normally

from a liquid radwaste evaporator. The vapor from this evaporator

released directly to the environment. 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 no

contained in this information notice are not NRC requirements; therefore, specific action or written response is required.

Description of Circumstances

On April 5, 1995, the licensee for the Hope Creek Nuclear Station, the Public

Service Electric & Gas Company, was using the decontamination solution

evaporator to process liquid waste from the chemical waste tank. The

evaporator was equipped with a demister and an exhaust vent piped directly to, the south plant vent. On two occasions, alarms caused by high differential The

pressure across the demister prompted the operator to spray the demister.

spraying, combined with a continuous supply of heating steam to increasethe

evaporator, caused a buildup of steam in the vapor body and an in

evaporator pressure, which was suddenly relieved when the operator stopped

spraying.

Unknown to the operator, these two depressurizations caused two momentary high

steam flows in the 15-cm-diameter [6-in-diameter] effluent exhaust pipe from

the evaporator, ejecting 227 L [60 gal] of approximately 26 MBq/L [0.7ofpCi/mL] the

radioactive water and steam mixture to the south plant vent upstreamestimated

effluent radiation monitor. About half this liquid, containing an

3,100 MBq [85 mCi] of mixed corrosion products, was released to the

environment and blown downwind, thus contaminating a large area within the

site protected area as well as onsite buildings and vehicles. The remainder

of the mixture was deposited as radioactive liquid in the south plant vent

ducting, thus causing radiation alarms in the nearby reactor building the

ventilation system exhaust and radwaste area exhaust systems. However, south plant vent effluent monitor did not indicate any ongoing or previous

9509280321 ID& It E t otk. S- qs-io

10\10VA VA x oi 5-q s10

K>i IN 95-46 October 6, 1995 release to the environment, even though the mixture passed isokinetic sampling

probes in the exhaust duct. These releases occurred between midnight and

1:00 a.m.

The licensee initiated abnormal operating procedures and an investigation. 1.2 after observing a hot spot in the south plant vent duct (approximately 30 cm [1 ft])

mSv/hr [120 mrem/hr] on contact and 0.15 mSv/hr [15 mrem/hr] at

and a radioactive reddish-brown liquid dripping from the duct into a

previously installed drip bag. Despite these indications, the licensee

believed no release had occurred because a sample of the evaporator effluent

indicated no unusual conditions and because the south plant vent effluent sample.

monitor did not indicate any abnormal radioactivity on an effluentcondition and

The licensee assumed the reddish liquid drip to be a preexisting a piece of

that the hot spot was caused by a piece of solid material (possibly

a filter) that had been deposited in the duct. The licensee focused on

preventing a release of radioactivity from occurring once the radioactive

liquid drips subsequently dried. The licensee also attempted to locate the

source and the extent of contamination.

While questioning plant staff during the afternoon shift turnover, the of

licensee also surveyed the turbine building roof and found elevated levels and found

removable contamination. The licensee then surveyed the yard areas

radioactive contamination in the protected area at approximately 4:00 p.m.

Vehicles that had left the site the day of the release were identified, located, and surveyed.

Discussion

The NRC review of the event is documented in NRC Inspection Report No.

50-354/95-05, dated May 30, 1995. The release of radioactive contamination

did not have a significant radiological impact on the public, were onsite workers, or the environment. However, several significant weaknesses revealed:

insufficient understanding and review of the design basis and operation of the

decontamination solution evaporator and the south plant vent effluent

monitoring system, inadequate communications and integrated assessment of

in accordance with

incoming information, operation of the evaporator neither Analysis

its design basis nor with commitments in the Final Safety Report, an

erroneous belief, unchallenged by several 10 CFR 50.59 safety evaluations, that the evaporator could not cause a radioactive release, and untimely

notification of workers of the release and onsite contamination.

Although radwaste systems typically are not safety related, proper operation

of such systems is essential for controlling onsite and offsite personnel

exposures within the limits of Parts 20 and 50 of Title 10 of the Code of

Federal Regulations.

This event and an event at the James A. FitzPatrick Nuclear Power below), Plant, which

notice 91-40 (referenced have

was discussed in a previous information operating

common root causes: weaknesses in design review or implementation, procedures, and management oversight of radwaste system operations.

IN 95-46 October 6, 1995 Related Generic Communications

Information Notice 91-40, Contamination of Nonradioactive System and

Resulting Possibility for Unmonitored, Uncontrolled Release to the

Environment,* June 19, 1991.

Circular No. 80-18, "10 CFR 50.59 Safety Evaluations for Changes to

Radioactive Waste Treatment Systems,' August 22, 1980.

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 Office of

Nuclear Reactor Regulation (NRR) project manager.

HY . orr

Division of Reactor rogram Management

Office of Nuclear Reactor Regulation

Technical contacts: Ronald L. Nimitz, RI John White, RI

(610) 337-5267 (610) 337-5114 Tracy Walker, RI Scott Morris, RI

(610) 337-5381 (609) 935-3850

Attachment:

List of Recently Issued NRC Information Notices

K- \.^Aachment

IN 95-46 October 6, 1995 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

95-12, Potentially Nonconforming 10/05/95 All holders of OLs or CPs

Supp. 1 Fasteners Supplied by for nuclear power reactors.

A&G Engineering II, Inc.

95-45 American Power Service 10/04/95 All holders of OLs or CPs

Falsification of American for nuclear power reactors.

Society for Nondestructive

Testing (ASNT) Certificates

95-44 Ensuring Compatible Use of 09/25/95 All Radiography Licensees.

Drive Cables Incorporating

Industrial Nuclear Company

Ball-Type Male Connectors

95-43 Failure of the Bolt-Locking 09/28/95 All holders of OLs or CPs

Device on the Reactor for nuclear power reactors

Coolant Pump Turning Vane designed by Westinghouse

Electric Corporation (W).

95-42 Commission Decision on the 09/22/95 All holders of OLs or CPs

Resolution of Generic for nuclear power reactors.

Issue 23, "Reactor Coolant

Pump Seal Failure'

95-41 Degradation of Ventilation 09/22/95 All holders of OLs or CPs

System Charcoal Resulting for nuclear power reactors.

from Chemical Cleaning of

Steam Generators

95-40 Supplemental Information 09/20/95 All holders of OLs or CPs

to Generic Letter 95-03, for nuclear power reactors.

Circumferential Cracking

of Steam Generator Tubes'

95-39 Brachytherapy Incidents 09/19/95 All U.S. Nuclear Regulatory

Involving Treatment Commission Medical

Planning Errors Licensees.

95-38 Degradation of Boraflex 09/08/95 All holders of OLs or CPs

Neutron Absorber in for nuclear power reactors.

Spent Fuel Storage Racks

OL = Operating License

CP - Construction Permit

kJ-' IN 95-46 October 6, 1995 Related Generic Communications

Information Notice 91-40, "Contamination of Nonradioactive System and

Resulting Possibility for Unmonitored, Uncontrolled Release to the

Environment," June 19, 1991.

Circular No. 80-18, "10 CFR 50.59 Safety Evaluations for Changes to

Radioactive Waste Treatment Systems," August 22, 1980.

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 Office of

Nuclear Reactor Regulation (NRR) project manager.

orig /s/'d by DMCrutchfield

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Ronald L. Nimitz, RI John White, RI

(610) 337-5267 (610) 337-5114 Tracy Walker, RI Scott Morris, RI

(610) 337-5381 (609) 935-3850

Attachment:

List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

DOCUMENT NAME: 95-46.IN

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September xx, 1995 Related Generic Communications

Information Notice 91-40, "Contamination of Nonradioactive System and

Resulting Possibility for Unmonitored, Uncontrolled Release to the

Environment," June 19, 1991.

Circular No. 80-18, "10 CFR 50.59 Safety Evaluations for Changes to

Radioactive Waste Treatment Systems," August 22, 1980.

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 Office of

Nuclear Reactor Regulation (NRR) project manager.

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical Contacts: Ronald L. Nimitz, RI John White, RI

(610) 337-5267 (610) 337-5114 Tracy Walker, RI Scott Morris, RI

(610) 337-5381 (609) 935-3850

Attachment: List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

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September xx, 1995 Related Generic Communications

Information Notice 91-40, 'Contamination of Nonradioactive System and

Resulting Possibility for Unmonitored, Uncontrolled Release to the

Environment," June 19, 1991.

Circular No. 80-18, 010 CFR 50.59 Safety Evaluations for Changes to

Radioactive Waste Treatment Systems,* August 22, 1980.

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 Office of

Nuclear Reactor Regulation (NRR) project manager.

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical Contacts: Ronald L. Nimitz, RI John White, RI

(610) 337-5267 (610) 337-5114 Tracy Walker, RI Scott Morris, RI

(610) 337-5381 (609) 935-3850

Attachment: List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

DOCUMENT NAME: S:\DRPM SEC\HOPEVAPO.IN1 This document was reviewed by technical editing on 08/14/95.

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OFFICE PECB/DOTS* I REGI/D:DRSS* I ADM:PUB* I D:DSSA* I D:DOTS* I

NAME CVHodge CWHehl Tech Editor GMHolahan RLSpessard

DATE 09/14/95 08/15/95 08/14/95 08 16/95 08/18/95

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September xx, 1995 Related Generic Communications

Information Notice 91-40, *Contamination of Nonradloactive System and

Resulting Possibility for Unmonitored, Uncontrolled Release to the

Environment,' June 19, 1991.

Circular No. 80-18, 10 CFR 50.59 Safety Evaluations for Changes to

Radioactive Waste Treatment Systems,' August 22, 1980.

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 Office of

Nuclear Reactor Regulation (NRR) project manager.

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical Contacts: Ronald L. Nimitz, RI John White, RI

(610) 337-5267 (610) 337-5114 Tracy Walker, RI Scott Morris, RI

(610) 337-5381 (609) 935-3850

Attachment: List of Recently Issued NRC Infi ormation Notices / /

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DATE 95 08/15/95 08/16/95 108/18/95 09/y/95

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Information Notice 95-XX Related Generic Communications

Information Notice 91-40, "Contamination of Nonradioactive System and

Resulting Possibility for Unmonitored, Uncontrolled Release to the

Environment," June 1991 Circular No. 80-18, "10 CFR 50.59 Safety Evaluations for Changes to

Radioactive Waste Treatment Systems," [???], 1980

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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 contact(s) listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

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Dennis M. Crutchfield, Diregtor

Division of Reactor Piojeetllanagement

Office of Nuclear Reactor Regulation

Technical Contacts: Ronald L. Nimitz, RI John White, RI

(610) 337-5267 (610) 337-5114 Tracy Walker, RI Scott Morris, RI

(610) 337-5381 (609) 935-5373 Attachment:

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