Information Notice 1979-09, Spill of Radioactively Contaminated Resin

Spill of Radioactively Contaminated Resin

ML031180151
Person / Time
Site:	Indian Point, 05000000
Issue date:	03/30/1979
From:	NRC/IE
To:
References
IN-79-009, NUDOCS 7904300110
Download: ML031180151 (3)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON, D.C. 20555 March 30, 1979 IE Information Notice No. 79-09

Description of Circumstances

In May 1978, a spill of contaminated resin slurry occurred outside the

auxiliary building at the Crystal River Nuclear Power Plant, Unit No. 3.

A plant radioactive waste pump was being used to transfer resin from a

holdup tank inside the building, through a trailer-mounted control

station, into a shielded shipping cask. The cask and trailer, owned and

operated by a contractor, were located outside of plant buildings

because of space limitations. All hoses in the transfer line were metal

braided and all piping was steel except for a polyvinylchloride (PVC)

tee inside the trailer, where flush water could be added after each

transfer. Resin entered the cask through a fill cap where It was mixed

with a solidifying agent. An automatic isolation valve in the transfer

line was designed to close upon receipt of a high cask level signal from

level instrumentation on the fill cap. The resin spill occurred when

this valve closed prematurely; the resultant pressure surge caused the

PVC tee inside the trailer to break. Resin flowed from the broken tee

into the trailer sump. Bolted seams in the sump leaked, spilling resin

onto asphalt pavement under the trailer. Water from the spilled resin

slurry flowed into a nearby storm drain.

Factors contributing to the cause or consequences of the spill included:

use of a PVC pipe fitting in the resin transfer line, inadequate hydro- static test of the system before use, failure to leak test the trailer

sump, and insufficient precautions taken to mitigate the consequences of

a spill.

Technical Specifications require radioactive waste systems to be tested

and operated in accordance with procedures approved by licensee management.

It should be noted that this requirement applies to systems owned and/or

operated by contractors at licensed power reactors.

It is the responsibility of licensees to review equipment and procedures

used for the transfer of contaminated liquids, resins, and filter media

that differ from permanent systems described in the FSAR. Such equip- ment and procedures should include consideration of the following:

7904o0 0 10

IE Information Notice No. 79-09 March 30, 1979 1. Preoperational testing of systems, including interlocks and

automatic functions. These tests should assure the operability

of the systems (i.e., hydrostatic testing for transient loads, testing of sump integrity, testing of system interlocks, func- tional testing of level instrumentation, and verification of

proper valve line-ups).

2. Visual inspection of connections, temporary lines, and other

potential leak paths during transfer operations.

3. Means to promptly isolate leaks.

4. Establishment of adequate communications.

5. Means to control releases (i.e., capping of uncontrolled drains, use of barriers or dikes, use of controlled sumps, and protection

from inclement weather).

No specific action or written response to this Information Notice is

required. If you desire additional information regarding this matter, please contact the Director of the appropriate NRC Regional Office.

Enclosure:

List of IE Information

Notices Issued in 1979

IE Information Notice No. 79-09 March 30, 1979 LISTING OF IE INFORMATION NOTICES

ISSUED IN 1979 Information Subject Date Issued To

Notice No. Issued

Bergen-Paterson Hydraulic 2/2/79 All power reactor

79-01 facilities with an

Shock and Sway Arrestor

OL or a CP

Attempted Extortion - 2/2/79 All Fuel Facilities

79-02 Low Enriched Uranium

79-03 Limitorque Valve Geared 2/9/79 All power reactor

Limit Switch Lubricant facilities with an

OL or a CP

79-04 Degradation of 2/16/79 All power reactor

Engineered facilities with an

Safety Features OL or a CP

Use of Improper Materials 3/21/79 All power reactor

79-05 facilities with an

in Safety-Related Components

OL or CP

79-06 Stress Analysis of 3/23/79 All Holders of

Safety-Related Piping Reactor OL or CP

Rupture of Radwaste Tanks 3/26/79 All power reactor

79-07 facilities with an

OL or CP

Interconnection of 3/28/79 All power reactor

79-08 facilities with an

Contaminated Systems with

Service Air Systems Used OL and Pu Processing

As the Source of Breathing fuel facilities

Air

Spill of Radioactively 3/30/79 All power reactor

79-09 facilities with an

Contaminated Resin

OL