05000272/LER-1980-017-01, /01T-0:on 800328,during Review of Environ Qualification Documentation Required by IE Bulletin 79-01B, RCS Wide Range Pressure Transmitters Were Found Below Max Flood Level.Caused by Imposition of New Requirements

/01T-0:on 800328,during Review of Environ Qualification Documentation Required by IE Bulletin 79-01B, RCS Wide Range Pressure Transmitters Were Found Below Max Flood Level.Caused by Imposition of New Requirements

ML18082A180
Person / Time
Site:	Salem
Issue date:	04/11/1980
From:	Murphy M Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18082A178	List: 05000272/LER-1980-017, Forwards LER 80-017/01T-0 05000272/LER-1980-017-01, /01T-0:on 800328,during Review of Environ Qualification Documentation Required by IE Bulletin 79-01B, RCS Wide Range Pressure Transmitters Were Found Below Max Flood Level.Caused by Imposition of New Requirements
References
IEB-79-01B, IEB-79-1B, LER-80-017-01T, LER-80-17-1T, NUDOCS 8004150558
Download: ML18082A180 (4)

LER-1980-017, /01T-0:on 800328,during Review of Environ Qualification Documentation Required by IE Bulletin 79-01B, RCS Wide Range Pressure Transmitters Were Found Below Max Flood Level.Caused by Imposition of New Requirements

Event date:
Report date:
2721980017R01 - NRC Website

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Report Number:

80-17/0lT Report Date:

4/11/80 Occurrence Date:

3/28/80 Facility:

Salem Generating Station Public Service Electric & Gas Company Hancocks's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Potential Deficiency Regarding Environmental Qualification of Reactor Coolant System (RCS) Wide Range Pressure Transmitters CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 100%

DESCRIPTION OF OCCURRENCE:

During the review of environmental qualification documentation for equipment required for accident mitigation/shutdown as required by NRC Bulletin 79-0lB, it was found that the Reactor Coolant System wide range pressure transmitters, PT-403 and PT-405, are located below the maximum containment flood level following a major loss of coolant accident.

Qualification documentation provides adequate data demonstrating post-accident operability in a harsh environment for the transmitters but does not include data for submergence.

The two pressure transmitters and their output signal are utilized for the following control functions:

1.

Permissive interlock for opening manually the Residual Heat Removal System suction valves (lRHl and 1RH2) from No. 11 Reactor Coolant hot leg whenever Reactor Coolant System pressure is below a specified value.

These transmitters also provide for automatic closure of these valves whenever Reactor Coolant System pressure is above a specified value.

2.

Saturated pressure/saturated temperature computer calcu-lation display/recording for operator information on Reactor Coolant System subcooling (NUREG-0578 requirement) *

3.

Operation of the Pressurizer Overpressure Protection System (POPS) power operated-relief valves to prevent pressure transients during low temperature operation.

In addit~on, wide range pressure indication is utilized in the emer-gency instruction in determining the trip point for the Reactor Coolant Pumps following certain accidents.

80 0.4 15 0 5 5 s

• -...,!__.J --..__r LER 80-17/0lT DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Although Westinghouse has indicated that the devices would work in a submerged state due to the transmitter seal design, documentation is not available to us to support this contention.

ANALYSIS OF OCCURRENCE:

The maximum containment flood level at Salem has been calculated to be at Elevation 83'-l" (FSAR Q6.28).

This level is based upon a major loss of coolant aGcident (LOCA) with the accumulator inventories, spilled Reactor Coolant System inventory, and the entire contents of a 400,000 gallon Refueling Water Storage Tank (RWST) being the con-tributing* factors.

One wide range pressurizer pressure transmitter (PT-403) is at Elevation 80'-0" and the other transmitter (PT-405) is at Elevation 82'-4".

Under the conditions of flooding following a major LOCA, the functions performed by the wide range pressure transmitters are not required for operator response.

With a depressurized Reactor Coolant System, switchover,to recirculation can be accomplished without their use.

The functions of the transmitter (except POPS) are required for small LOCA's, steam line and feedwater line breaks where the Reactor Coolant System will not become totally depressurized.

The flood level from these type breaks will be less than Elevation 83'-l" due to the lower inventory of water discharging into the containment.

Transmitter PT-403 would probably become flooded following the event, wherea~

PT-405 would not.

During and. following the accident conditions.where the wide pressure transmitters would be required, at least one transmitter should remain above the expected flood level.

The transmitter design for these particular units is pressure sealed to prevent moisture leakage.

The instrument lead wires and connection to the signal cable are also sealed.

Although complete test data is not available, the design and installation of the units indicate that they would operate in a submerged state.

Preliminary indication from Westinghouse supports this contention.

Alternate backup indications are available to the operator during accident recovery to assist in the maintenance of adequate core cooling should the' wide range pressure transmitters not operate pr~perly due to potential flooding or random failure of the instru-ments.

The four pressurizer pressure transmitters can be utilized where the reactor coolant pressure is in the range of 1700-2500 psig.

These units are Rosemount 1153 Series A pressure transmitters and have adequate documentation demonstrating their operability in a post accident environment.

These pressure transmitters are located above the maximum flood level at Salem.

Additionally, Reactor Coolant System pressure can be estimated from the discharge pressure indica-tions for the Boron Injection Tank (charging) and t:be Safety Injection Pumps.

Flow indication is also provided to indicate to the operator that there is discharge flow to the Reactor Coolant System.

These

LER 80-17/0lT devices are safety grade and are located outside the containment and, therefore, are not subject to the accident environment.

The backup indications identified could be utilized by the operator, if required, in recovery operations.

During postulated post-accident operations when it becomes necessary to initiate closed loop cooling via the residual heat removal system suction from No. 11 Reactor Coolant hot leg, the pressure interlocks for the lRHl and 1RH2 valves can be jurnpered at the motor control centers to permit manual valve opening dependent upon backup pressure indication.

Although the automatic closure feature would be defeated, overpressurization of the residual heat removal system is prevented by relief valves until the operator manually closes the lRHl and/or 1RH2 valves from the Control Room.

CORRECTIVE ACTION

The Analysis of Occurrence above provides appropriate justification for the continued operation of Unit 1 until the wide range pressure transmitters are relocated.

The potential loss of both transmitters, when required, is not probable and, even if both should fail due to flooding, adequate backup indications are available and actions can be taken to maintain plant safety following an accident.

A design change has been prepared (lEC-0722) to relocate the PT-403 and PT-405 wide range pressure transmitters above the maxim:um flood level at Salem, and the design change is in the review process.

The work will be completed at the next appropriate shutdown.

The relocation with the present qualification documentation will provide adequate assurance that the transmitters will operate when required in a post-accident environment.

INSTRUMENT TYPE:

Barton Instruments Model 764, Lot 2 Prepared By J. M. Zupko, Jr.

SORC Meeting No.

24-80 Manager - SaJ.em GeeratiilgStation

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Bulletin 79-0lB, it was found that the Reactor Coolant System wide range pressure transmitters are located below the maximum containment flood level *. Qualification documentation provide adequate data for post-accident operability in a harsh environment but does not include data for submergence.

Alternate backup indications are available above the maximum flood level and could be used by the

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