ML18085A919

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Nonproprietary Version of Environ Qualification Review Rept, Vol 2,Revision 3
ML18085A919
Person / Time
Site: Salem  PSEG icon.png
Issue date: 02/09/1981
From:
Public Service Enterprise Group
To:
Shared Package
ML18085A914 List:
References
M-P81-11-06, M-P81-11-6, NUDOCS 8102260632
Download: ML18085A919 (48)
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{{#Wiki_filter:XI TMI ACTION ITEMS M P81 11/06 6 Rev. 3

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. 3. XI TMI ACTION ITEMS Bulletin 79-018, Supplement 3, "Environmental Qualification of Class IE Equipment" requires that the Environmental Qual-ification Review Report for Salem include qualification in-formation on installed TMI Action Plan equipment. Qualifi~ cation information on future TMI Action Plan equipment will be submitted by the pre-implementation review data. The following items have been installed under the TMI category which must.be operable under harsh environment conditions: Item Pressurizer Power Operated Relief Valve ( PORV) Indication Pressurizer Safety Relief Valve Indication Containment Water Level Indication Devices NAMCO EA-180 limit switches for valves PRl, PR2 NAMCO EA-180 limit switches for valves PR3, PR4, PR5 Master List pg s. 2 8 ' 2 9 ' 3 1 ' 3 2 pgs. 28, 29, 31, 32 GEMS Model Number pgs. 475-483 XM60175, XM60174, XM6 0173, RE6 0172 Remarks Qualified Qualified Undergoing Qualifica-tion Testing The GEMS water level indication system has been installed to replace the previous sump level indication system which was included in our master list on pages 342-345. The contain-ment water level indication is not required by the operator to take safety actions during the course of an accident. The new system was installed to provide direct indication of* water level instead of alarm levels. It has been designed so as to be operable during accident conditions and provide the operator with additional information on containment con-ditions. The GEMS system will be tested to assure its qual-ification for accident use. Plant safety is not compromised while this qualification testing is performed to provide adequate documentation to verify the design capabilities. The testing is planned to be complete by the end of 1981 and the documentation will be submitted when available. M P81 11/06 2 Rev. 3

XII COLD SHUTDOWN REQUIREMENTS M P81 11/06 3 Rev. 3 J

XII COLD SHUTDOWN REQUIREMENTS Bulletin 79-0lB, Supplement 3, "Environmental Qualification of Class IE Equipment" requires that the Environmental Qual-ification Review Report for Salem include identification of equipment needed to complete one method of achieving and maintaining a cold shutdown condition. The staff position is also that the licensee must environmentally qualify this equipment. The Salem plant has been designed on the basis 0£ hot shut-down/recirculation under accident conditions. Cold shutdown is not a design basis for Salem. TM! and related activities have focused attention on cold shutdown capability following accidents. The Westinghouse Owners Group has investigated the methodology for achieving cold shutdown under adverse conditions and has prepared preliminary guidelines. De-tailed plant specific emergency operating procedures have not yet been prepared but studies are continuing in this area. PSE&G has examined equipment needed to achieve cold shutdown utilizing a method identified by the Own~rs Group. Much of the equipment has already been included in the report be- *

  • cause of its use in hot shutdown/recirculation to maintain stable plant conditions.

However, some equipmen.t which is acceptable for hot shutdown/recirculation does not have ade-quate documentation to support its use in long term cooldown and depressurization of the reactor coolant system. Some new equipment has also been added to the report. The following Part A provides a brief outline of the cold shutdown scenario. Part B provides a short description of new items needed where information is provided in the Master List. Part C identifies the principal items that were in the Environmental Qualification Review Report and are needed for cold shutdown. Part D discusses the problems encoun-tered and remedies to correct the situation to meet the NRC Staff position promulgated in Bulletin 79-0lB. This infor-mation is provided as requested in the Bulletin although hot shutdown/recirculation is the Salem design basis. PSE&G will make every attempt to comply with the staff position to have a method and its equipment environmentally qualified by June 30, 1982. M P8.l 11/06 4 Rev. 3

Part A - Cold Shutdown Scenario The following is a brief description of the principal func-tions utilized: Long Term Reactivity Control and Makeup The principal sources of boron are the boron injection tank (BIT), the refueling water storage tank (RWST), and the boric acid tanks (BAT). In the event emergency boration is necessary, the *boric acid tanks provide sufficient boric acid to achieve cold shutdown. Rapid boration is accom-plished utilizing the boric acid transfer pumps and the charging pumps. Additional makeup for reactor coolant shrinkage and to m~intain pressurizer level will be pr6vided by the RWST via the charging pumps and the BIT. The letdown line is isolated and not used during post-accident cooldown. Cool down The auxiliary feedwater system and the main steam power operated atmospheric relief-valves will be utilized for initial cooldown. Margin to saturation will be maintained by the operator monitoring pressurizer pressure, RCS temper-* ature and reactor coolant pressure. While discharging steam, the auxiliary feedwater flow will be controlled to maintain steam generator level. When the RCS is cooled down sufficiently, the re~idual heat removal (RHR) system will be engaged to continue _the coOldown to iess than 200°F. If core damage is evident and hi~h activity levels exist, re-circulation will *not begin until the RWST is empty to assure the RCS and containment sump inventory activity levels have been reduced by dilution. Cooldown of the reactor coolant system may involve recirculation from the sump and the nor-mal reactor coolant shutdown line for residual heat removal depending on the type accident. Reactor Coolant System Depressurization The PORV's will be utilized to depressurize the RCS. The operator will monitor pressurizer pressure, RCS temperature, and reacior coolant pressure as the RCS is depressurized to ensure a margin to saturation is maintained. M P81 11/06 5 Rev. 3

Part B - New Items Located in Harsh Environment Item

1.

Boric Ac id Transfer Pumps .2. Heat Tracing

3.

Pump Room Coolers (motors, solenoids and temperature switches)* Master List page 131A page 131A pgs. 484-502 Remarks Undergoing review Qualified Motor undergoing review, sole-noids need replacement and procedure change Part C - Existing Items in Report Utilized Item Master List Remarks

1.

Main Steam Atmospheric pgs. 62-77 Relief Valves (MSlO) Upgrade

2.

Steam Generator Level pgs. 46-61 Qualified Basis #2

3.

Pressurizer Pressure pgs. 18-21 Qualified

4.

Reactor Coolant Pressure

5.

Reactor Coolant Temperature (wide range)

6.

Pressurizer Power Operated Relief Valves (solenoids for control)

7.

Pressurizer PORV Block Valves

8.

Charging System MOV's pgs. 13-17 pgs. 9-12, 17 Qualified Basis #2 Qualified pgs. 22-24, 31, Upgrade for long term manipulation pgs. 25-27, 31 Upgrade motors for long term manipulation pgs. 124, 125, Qualified 127, 128, 129

9.

Charging Pumps (motors) pgs. 125, 130 Qualified M P81 11/06 6 Rev. 3

Item

10. RHR MOV's
11. RHR Pumps (motors)

Master List pgs. 152-154, 156-158, 168-182 pgs. 150, 151

12. Containment Ventilation pgs. 300-326
13.

Accumulator Isolation pgs. 456-462 MOV's Part D - Problem Area Discussion Remarks Qualified Qualified Qualified with actions noted in Bases 19' 20 Upgrade motors for long term manipulation The following is a discussion of the areas reviewed and the problems encountered in qualification documentation for the above noted items: Boric Acid Transfer Pump Motors These devices were supplied by Westinghouse. Qualifica-tion documentation exists.for out-of-containment.Class IE motors supplied byWestinghouse (of which this is one). A review will be made to assure that this motor is of the same design as those qualified. **.The radiation level is very low (<103R) and there is no reason to expect that they would not operate. Room Cooler Motors These devices are only exposed to high radiation due to recirculation. They provide supplemental cooling to the pump rooms. Radiation data is being requested from the manufacturer to assure operability. The motors could be replaced with qualified ones if necessary. Portable fan install~tion could be utilized if motors *should fail to provide supplemental cooling. Room Cooler Temperature Switches A temperature switch. operates the room cooler when in the auto mode. No qualification data is currently available M P81 11/06 7 Rev. 3

on these switches. To eliminate the dependence on these - switches, operating procedures can be revised to instruct the operator to place the room coolers in the manual mode during accident conditions.* In this mode the coolers are energized, and will continue to operate until they are. manually shut off. Subsequent misoperation of the switch will not affect room cooler operation. Room Cooler Solenoid Valves These solenoid valves control the room cooler exhaust dampers and service-water inlet valves to the room*coolers and lube oil coolers. No qualification data is available on these valves. Radiation is the harsh environment for these valves. Once the pump runs, the lube oil cooler valves deenergize providing service water flow. Once the room cooler operates, the solenoids deenergize providing service water flow to the coolers. Once deenergized there is no failure mechanism which could cause reenergization and stoppage of cooling water flow. The coolers and pumps are operable prior to their being exposed to high radia-tion levels. In addition, the operators could be in-structed to deenergize the_ circuit at the breaker to as-sure that service water flows to the coolers. PORV Block Valves The PORV Block Valves are closed during initial stages of - an accident. The Limitorque valve motors have Class "B" insulation which is only qualified for fotir hours inside containment. Since the PORV's will be utilized to depres-surize.the RCS following an accident, the stop valves must be qualified for the duration of the accident to reopen. The valve motor operators can be replaced with Class "H" insulation for long term operability. An alternate to PORV depressurization is a slow method utilizing secondary side systems. - Unit 1 PORV Air Supply Solenoids Solenoid Valves SV-1198 and 1199 control the air supply to the PORV's. These valves are currently not qualified.

  • Air accumulators are part of the current Unit 1 PORV de-sign and provide control air in the event instrument air is lost. -This was supplied for the Pressurizer Overpres-sure Protection System.

Since the PORV's will be used for depressurization, a qualified air supply must be pro-vided. These solenoids can be replaced *with Asco NP series. An alternate to PORV depressurization is a slow method utilizing secondary side systems. M P81 11/06 8 Rev. 3

- Unit 2 PORV 1 s

  • Unit 2 does not have an accumulator air supply to the PORV's in the event of a loss of instrument air for the Pressurizer Overpressure Protection System.

To qualify the pressure relief system for long term operation, either an accumulator system is needed or the solenoid operated bypass valves 2PR47 and 2PR48 must be qualified. 2PR47 and 2PR48 would perform the pressure relief function if the PORV's fail to operate. An alternate to the PORV's is slow depressurization by cooling down with the secondary side of the plant. Main Steam Atmospheric Relief Valves (MSlO) The MSlO's currently are controlled through an unqualified electric/pneumatic converter and pressure transmitter. Since the MSlO's will be utilized to cooldown the RCS fol-lowing an accident, a qualified control scheme is re-quired. The valves can also be operated manually. If the cause of the accident is a break outside of containment, an operator can be sent to manually modulate the valve. If the break is inside containment, the plant can remain in hot standby until radiation levels are low enough to send an operator to the main stream penetrations for man-ual manipulation. Accumulator Isolation Valves Before the RCS is depressurized below 700psi, the isola-tion valves should be closed to prevent dumping the con-tents of the accumulators. Several of the valve motor operators are Limitorque with Class "B" insulation which are not qualified for long term operation inside contain-ment. The valve motors can be replaced with the fully qualified type with Class "H" insulation. An analysis will be performed to determine the effect of the accumula-tors inadvertently dumping into the RCS during cooldown. A safety_hazard is not envisioned. The above discussion provides possible ways of meeting the Staff position on cold shutdown by replacement of equipment and procedure changes. Alternatives are provided where necessary. The entire concept is still undergoing review by PSE&G as well as industry study groups. A firm schedule on the necessary upgrades for cold shutdown equipment will be provided later once the methodology/procedures are confirmed and finalized. We hope this can be done by May, 1981. M P81 11/06 9 Rev. 3

M P81 11/06 SALEM GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-272 AND 50-311 ENVIRONMENTAL QUALIFICATION REVIEW REPORT VOLULME 2 (NON-PROPRIETARY VERSION) December 1, 1980 Rev. 1 - l 2/ 1/8 0 Rev. 2 - 1/16/81 Rev. 3 - 2/9/81

System Name Reactor Coolant Pressurizer Main Stearn MASTER LIST OF EQUIPMENT Main Feedwater Auxiliary Feedwater Charging and Letdown Safety Injection Residual Heat Removal Containment Spray Component Cooling Containment Isolation Containment Ventilation Combustible Gas Controls Containment Parameters Miscellaneous Accumulators Containment Water Level - TMI Auxiliary Building Ventilation M P80 108 02/16 Page No. 1-17 18-39 40-109 110-111 112-117 118-131A 132-149 150-182 183-198 199-203 204-299 300-326 327-333 334-399 400-455 456-474 475-483 484-502 Rev. 3

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