Information Notice 1980-37, Containment Cooler Leaks & Reactor Cavity Flooding at Indian Point Unit 2

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Containment Cooler Leaks & Reactor Cavity Flooding at Indian Point Unit 2
ML031180421
Person / Time
Site: Indian Point, 05000000
Issue date: 10/24/1980
From:
NRC/OI
To:
References
IN-80-037, NUDOCS 8008220249
Download: ML031180421 (3)


SSINS No.:

6835 Accession No.:

8008220249 UNITED STATES

IN 80-37

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND.ENFORCEMENT

'HASHINGTON, D.C.

20555

October 24, 1980

IE Information Notice Mo. 80-37: CONTAINMENT COOLER LEAKS AND REACTOR CAVITY

FLOODING AT INDIAN POINT UNIT 2

Discription of Circumstances:

This Notice contains information regarding multiple service water leaks into

containment with resulting damage to reactor instrumentation and potential

damage to the reactor pressure vessel.

Upon-containment entry on October 17, 1980 at Indian Point Unit 2, to repair a

malfunctioning power range nuclear detector, it was discovered that a significant

amount of water was collected (approximately 100,000 gal) on the containment

floor, in the containment sumps, and in the cavity under the reactor pressure

vessel (RPV). This collected water probably caused the detector malfunction, and the water in the cavity under the RPV is believed to have been deep enough

to wet several feet of the pressure vessel lower head, causing an unanalyzed

thermal stress condition of potential safety significance.

This condition resulted from the following combination of conditions:

(1) Both containment sump pumps were inoperable, one due to blown fuses from an

unknown cause and the other due to binding of its controlling float; (2) The

two containment sump level indicating lights which would indicate increasing

water level over the water level range present in the containment were stuck

(on) and may have been for several days, leaving the operator with no operable

instrumentation to measure water level in the containment; (3) The moisture

level indicators in the containment did not indicate high moisture levels, apparently because they are designed to detect pressurized hot water or steam

leaks (i.e., a LOCA), and are not sensitive to the lower airborne moisture levels

resulting from relatively small cold water leaks; (4) The hold-up tanks which

ultimately receive water pumped from the containment sump also receive Unit 1 process water, lab drain water, etc. These other water sources masked the effect

of cessation of water flows from the Unit 2 sump; (5) There were significant, multiple service water leaks from the containment fan cooling units directly

onto the containment floor. These coolers have a history of such leakage, which

cannot be detected by supply inventory losses since the supply system (service

water system) is not a closed system; (6) The two submersible pumps in the cavity

under the Reactor Pressure Vessel were ineffective since they pump onto the con- tainment floor for ultimate removal by the (inoperable) containment sump pumps.

There is no water level instrumentation in the cavity under the RPV, nor was

there any indication outside the containment when these pumps are running.

The licensee has installed redundant sump level annunciated alarms in the

control room and has installed an annunciated alarm in the control room to

indicate if either submersible pump in the reactor cavity activates. The

licensee has also repaired the service water leaks, installed guide bushings

on the sump pump control floats to prevent their binding, and has repaired

the containment sump water level indicators.

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IN 80-37 October 24, 1980 The licensee plans in the loncer term to replace the containment fan unit

cooling coils.

It is anticipated that results of a continuing NRC investigation into this

incident will result in issuance of an IE Bulletin and/or an NRR Generic

Letter in the near future which will recommend or require specific licensees

and applicant actions.

In the interim, we recommend that all licensee

ascertain that the potential does not exist for undetected water accumulation

in the containment.

This Information Notice is provided to inform licensees of a possibly significat

matter.

No written resoonse to this Information Notice is required.

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IN 80-37

October 24, 1980

RECENTLY ISSUED

TE INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issue

Issued to

80-36

80-35

80-34

80-33

80-32

80-31

80-30

80-29

Failure of steam

generator support bolting

Leaking and dislodged

Iodine-124 implant seeds

Boron dilution of reactor

coolant during steam

generator decontamination

Determination of teletherapy

timer accuracy

Clarification of certain

requirements for Exclu- sive-use shipments of

radioactive materials

Maloperation of Gould-

Brown Boveri Type 480

volt type K-600S and

K-DON 600S circuit

breakers

Potential for unaccept- able interaction between

the control rod drive scram

function and non-essential

control air at certain GE BWR

facilities

Broken studs on Terry

turbine steam inlet

flange

10/10/80

10/10/80

9/26/80

9/15/80

8/12/80

8/27/80

8/19/80

8/7/80

All nuclear power

reactor facilities

holding OLs or CPs

All categories G and

G1 medical licensees

All pressurized water

reactor facilities

holding power reactor OLs

All teletherapy

(G3) licensees

All NRC and agreement

state licensees

All light water reactor

facilities holding OLs

or CPs

All boiling water reactor

facilities holding power

reactor OLs or CPs.

All light water reactor

facilities holding

power reactor OLs or CPs*

Supplement to

80-06

Notification of

significant events at

operating power reactor

facilities

7/29/80

All holders of reactor

and near-term OL

applicants

80-23

Prompt reporting of

required information

to NRC

6/13/80

All applicants for

holders of nuclear

reactor CPs

and

power

  • Operating Licenses or Construction Permits