Information Notice 1979-22, Qualification of Control Systems

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Qualification of Control Systems
ML031180167
Person / Time
Site: 05000000
Issue date: 09/14/1979
From:
NRC/IE
To:
References
IN-79-022, NUDOCS 7908220124
Download: ML031180167 (3)


Accession No: 790822011 SSINS: 6870

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON, D.C. 20555

September 14, 1979

IE Information Notice No. 79-22

QUALIFICATION OF CONTROL SYSTEMS

Public Service Electric and Gas Company notified the NRC of a potential unreviewed

safety question at their Salem Unit 1 facility. This notification was based on a

continuing review by Westinghouse of the environmental qualifications of equipment

that they supply for nuclear steam supply systems. Based on the present status

of this effort, Westinghouse has informed their customers that the performance

of non-safety grade equipment subjected to an adverse environment could impact

the protective functions performed by safety grade equipment. These non-safety

grade systems include:

Steam generator power operated relief valve control system

Pressurizer power operated relief valve control system

Main feedwater control system

Automatic rod control system

These systems could potentially malfunction due to albigh energy line break

inside or outside of containment. NRC is also concerned that the adverse

environment could also give erroneous information to the plant operators.

Westinghouse states that the consequences of such an event could possibly be

more limiting than results presented in Safety Analysis Reports, however, Westinghouse also states that the severity of the results can be limited

by operator actions together with operating characterisitics of the safety

systems. Further, Westinghouse has recommended to their customers that they

review their systems to determine whether any unreviewed safety questions exist.

This Information Notice is provided as an early notification of a possibly

significant matter. It is expected that recipients will review the information

for possible applicability to their facilities. No specific action or response

is requested at this time. If NRC evaluations so indicate, further licensee

actions may be requested or required.

If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.

No written response to this Information Notice is required.

.

I

._. 'A

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IE Information Notice No. ; 22

September 14, 1979 LISTING OF IE INFORMATION NOTICES

ISSUED IN LAST SIX MONTHS

Information

Notice No.

Subject

Date

Issued

Issued To

79-05

79-06

79-07

79-08

79-09

79-10

Use of Improper Materials

in Safety-Related Components

Stress Analysis of

Safety-Related Piping

Rupture of Radwaste Tanks

Interconnection of

Contaminated Systems with

Service Air Systems Used

As the Source of Breathing

Air

Spill of Radioactively

Contaminated Resin

Nonconforming Pipe

Support Struts

Lower Reactor Vessel Head

Insulation Support Problem

Attempted Damage to New

Fuel Assemblies

Indication of Low Water

Level in the Oyster Creek

Reactor

NRC Position of Electrical

Cable Support Systems

Deficient Procedures

3/21/79

All power reactor

facilities with an

OL or CP

3/23/79

All Holders of

Reactor OL or CP

3/26/79

All power reactor

facilities with an

OL or CP

3/28/79

All power reactor

facilities with an

OL and Pu Processing

fuel facilities

3/30/79

All power reactor

facilities with an

OL

4/16/79

All power reactor

facilities with a

CP

79-11

5/7/79.

.;4.

All holders of Reactor

OLs and CPs

79-12

79-13

5/11/79

All Fuel Facilities

Research Reactors, and Power Reactors

with an OL or CP

5/29/79

All Holders of Reactor

OLs and CPs

6/11/79

All Power Reactor

Facilities with a

CP

79-14

79-15

6/7/79

All Holders of Reactor

OLs and CPs

I

IE Information Notice No. 79-22

September 14, 1979

LISTING OF IE INFORMATION NOTICES

ISSUED IN 1979 Information

Notice No.

Subject

Date

Issued

Issued To

79-16

79-17

79-18 Nuclear Incident at Three

6/22/79

All Research Reactors

Mile Island

and Test Reactors

with OLs

Source Holder Assembly Damage 6/20/79

All Holders of Reactor

Damage From Misfit Between

OLs and CPs

Assembly and Reactor Upper

Grid Plate

Skylab Reentry

7/5/79 All

OLs

Holders of Reactor

79-19

Pipe Cracks In Stagnant

Borated Water Systems At

PWR Plants

7/17/79 All Holders

OLs and CPs

of Reactor

79-20

79-21 NRC Enforcement Policy

8/10/7'

NRC Licensed Individuals

Transportation and Commercial 9/7/79

Burial of Radioactive Material

'9 All Holders of Reactor

OLs and CPs and Production

Licensees with Licensed

Operators

All power and research

reactors with OL's

No.