ML19290E231

Submits Present Status of Each NUREG-0578 Item Covering Emergency Power Supply,Containment Isolation & Auxiliary Feedwater Flow

ML19290E231
Person / Time
Site:	Beaver Valley
Issue date:	02/29/1980
From:	Dunn C DUQUESNE LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8003050510
Download: ML19290E231 (10)

Text

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'Af (412) 456-6000 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 February 29, 1980 Director of Nuclear Regulation United States Nuclear Regulatory Commission Attention: D. G. Eisenhut Division of Operating Reactors Washington, D.C. 20555

Reference:

Beaver Valley, Power Station, Unit No. 1 Docket No. 50-334 Discussion of Lessons Learned Short Term Requirements Gentlemen:

The present status of each NUREG 0578 item follows:

Section 2.1.1 - Emergency Power Supply - Pressurizer Heater The Pressurizer Back Up Heaters are capable of being manually connected to the Class IE electrical buses. A total of 485 KW in 2 groups of 270 and 215 KW can be connected to each of the two diesel generators. This capacity exceeds the 400 KW required to maintain subcooled conditions for a 1400 cubic foot pressurizer. The manner in which these connections are presently made meets all requirements in your October 30, 1979 letter.

Emergency Power Supply for Pressurizer Relief and Block Valves and Pressurizer Level Indication The power supply for these items meets all the requirements of the Staff Position and the clarification provided in your October 30, 1979 letter.

The DC solenoid valves which provide air to the diaphragm operated PORVs are powered from a station battery that is not associated with the battery that powers the solenoids used on the air starting motors for the diesel generator that powers the associated PORV Block Valve. We believe that this arrangement meets the requirements of the staff position.

We, therefore, plan to retain the existing power circuitry for the PORV Block Valves.

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Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Discussion of Lessons Learned Short Term Requirements Page'2 The air supply for the Power Operated Relief Valves is powered by the containment air compressors which are capable of being powered by the Diesel Generators. We have also provided a nitrogen supply back up for these valves as described in our submittal on the Reactor Vessel Overpressure Protection System. In addition, Beaver Valley has installed a diesel drivan air compressor which can be manually loaded onto the normal station air system.

We have successfully utilized this diesel air compressor in the past during a loss of station power and believe it to be a reliable source of back up air. This diesel driven air compressor is not classified as Category I and no Category I type qualification papers exist for this air compressor. We have no plans to attempt to upgrade this air compressor to Category I since such an exercise would not improve the presently satisfactory reliability of this equipment which for the PORVs represents a back up to a back up air supply. The steam generator level instruments are presently supplied from the station vital buses.

Section 2.1.2 As previously discussed, we are participating in the EPRI sponsored testing program. We believe that this program is being conducted in accordance with the staff requirements as clarified. The program shall be submitted by Mr. Cordell Reed, Chairman of the TMI Owners Group of Westinghouse plants.

Section 2.1.3(a) - Direct Ind'. cation of PORVs and SVs We will provide indication of the position of the Pressurizer Relief Valves and Power Operated Valves prior to station start up in 1980. Acoustic monitors will be attached to each PORV and Relief Valve to detect flow through the valves. Signals from the acoustic pickups will be transmitted to a cabinet outside containment and the cabinet will provide both position indication and alarms to the Control Room. These indications will comply with the clarifications provided in your October 30, 1979, letter.

Section 2.1.3(b) - Subcooling Meter We are presently evaluating proposals received from the various vendors of subcooling meters. We do not plan to utilize the plant computer for this application and will provide a back up procedure based upon the use of steam tables and/or saturation pressure / temperature curves.

The saturation meter which will be installed and operational at Beaver Valley prior to station start up in 1980 will comply with all staff require-ments as clarified in your October 30, 1979, letter. The detailed information requested on pages 11 and 12 of Enclosure No. 1 in your October 30 letter will be submitted as soon as possible after placement of the purchase order for this device.

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Discussion of Lessons Learned Short Term Requirements Page 3 This monitor is to use existing pressure and temperature instruments and incore thermocouples to determine the saturation pressure for any incore or loop temperature.

The proposed subcooling monitor meter is divided into three regions.

The extreme left end indicates invalid results either due to unit failure or invalid inputs. The region between the left invalid region and the saturation point (just to the right of center) is the margin to saturation in psi. This margin to saturation is the system pressure minus the satu-ration pressure. The saturation pressure is calculated from either the highest RTD gT or TC if the selector is in the RTD position or the highest Thermocouple if the selector is in the T/C position.

The region to the right of the saturation point (0 psi mark) is degrees superheat and indicates that the highest temperature and the lowest pressure indicate superheated steam conditions. The degrees superheat region is linear from saturation (0 degrees superheat) up to 50*F superheat. Beyond 50*F super-heat the scale is logarithmic up to 2000 F superheat.

The monitor is equipped with two levels of alarm. The lower alarm or caution is indicated by a yellow temperature status light on the menitor and the actuation of a set of contacts to the plant annunciator panel. The second alarm is indicated by a red temperature status light and the acutation of a second set of contacts to the plant annunciator panel.

Section 2.1.3(c) - Additional Instrumentation We are currently investigating the feasibility of installing reactor vessel level instrumentation to monitor the water level in the reactor vessel. A design change has been initiated to install pressure taps at various locations in the reactor coolant system to allow later installation of the level instru-centation.

Section 2.1.4 - Containment Isolation Containment Isolation is initiated at Beaver Valley by the following diverse means:

1. Containment Pressure and

2. Safety Injection Since the Safety Injection Signal is generated when various and diverse reactor coolant system parameters, and/or steam and feedwater system parameters either individually or in combination reach values which have been determined by analyses to signify the occurrence of, or approach to, a transient or accident condition which requires the actuation of the Emergency Core Cooling System.

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Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Discussion of Lessons Learned Short Ters Requirements Page 4 The design of the control systems for the automatic containment isolation valves which are actuated by these signals is such that a resetting of the isolation signal will not result in the automatic reopening of any containment isolation valve.

We have reviewed all mechanical systems which enter and exit the containment structure to determine whether they had been properly categorized as essential or nonessential. The results of this review, which were sent to you on February 8, 1980, indicated that no modifications to the containment isolation design are required.

Section 2.1.5(a) - Dedicated H Control Penetration Beaver Valley is equipped with combined design containment penetrations which have been properly sized for the two permanently installed Atomics -

International Hydrogen Recombiners. A tap is provided for the two 5 cfm vacuum pumps which are periodically operated in a manual mode during operation to maintain sub atmospheric conditions within the containment structure. The vacuum pumps are automatically isolated -from the recombiners on a containment isolation signal. The design of the existing redundant hydrogen recombiner system is single failure proof. The Hydrogen Recombiner System is described in Section 6.5 of the FSAR for Beaver Valley. The existing design meets the requirements of GDC54 and GDC56 with the exceptions noted in the Beaver Valley FSAR.

Section 2.1.5(c) - Capability to Install H Recombiner 2

The Hydrogen Recombiners at Beaver Valley are permanently installed. These recombiners are started from a local control panel located with the recombiners.

The shielding and associated personnel limitations associated with the use of the recombiners are presently under review.

We shall prepare detailed operating procedures for the use of these recom-biners which take into account the experience gained at IMI and consider personnel limitations that are identified in the shielding review.

The procedures shall be available prior to the post refueling start up in mid-1980.

Section 2.1.6(a) - Integrity of Systems Outside Containment Likely to Contain Radioactive Materials A program to reduce leakage from systems outside containment that would, or could, contain highly radioactive fluids during a serious transient or accident condition is being prepared.

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Discussion of Lessons Learned Short Term Requirements Page 5 This program will include an examination of methods to reduce leakage potential release paths due to design and operator deficiencies as discussed in your letter of October 17, 1979.

This program will be instituted and fully implemented prior to returning the Beaver Valley Power Station to power operatica following the extended refueling and modification outage.

Section 2.1.6(b) - Design Review of Plant Shielding and Environmental Qualification of Equipment for Spaces / Systems Which May Be Used in Post Accident Operations A review of plant shielding has been performed in accordance with the staff position as clarified. Necessary plant or procedural modifications have been identified and all procedural modifications shall be implemented prior to the restart of the plant in mid-1980. All possible plant modifications shall be completed by January 1, 1981.

Section 2.1.7(a) - Auto Initiation of the Auxiliary Feedwater System Automatic / Manual Initiation of the Auxiliary Feedwater System is presently available at Beaver Valley. These circuits are presently tested periodically in accordance with the Beaver Valley, Unit No. 1 Maintenance Surveillance Test Program. All motor operated pumps and valves are included in the automatic sequencing of loads to the emergency buses. A failure of the automatic initiation circuitry will not result in a loss of =anual start capability from the control room. Instrument air is not required for the operation of the auxiliary feedwater system at Beaver Valley.

Section 2.1.7(b) - Auxiliary Feedwater Flow Indications in Steam Generators The Beaver Valley Power Station presently has control grade auxiliary feedwater flow indication to each steam generator. Each single channel instrument is backed up by a steam generator level indication. We are presently engaged in engineering to upgrade the auxiliary feedwater flow indication to safety grade. This will require new power supplies and rerouting of cabling between the transmitters and the indicators. We are planning to complete this upgrade by December 31, 1980.

Section 2.1.8(a) - Improved Post Accident Sampling Capability We have performed a comprehensive review of plant post accident sampling and analytical capabilities including the capability to perform chemical analysis of highly radioactive samples. Plant procedures for the handling and analysis of such samples and all possible plant modifications to facilitate the required capability will be completed prior to the restart of the plant in 1980.

A schedule for the completion of all other modifications which have been deter-mined to be necessary will be forwarded as soon as a schedule for these activities.

is developed. All requirements as described in the clarifications on pages 27 through 30 of Enclosure 1 to your October 30, 1979, letter will be addressed.

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Discussion of Lessons Learned Short Term Requirements Page 6 Section 2.1.8(b) -

Increased Range of Radiation >bnitors Interim methods, utilizing grab samples and laboratory analyses, supplemented by continuously reading, recording and integrating PICS in downwind directions, will be used to quantify high level radioactive releases.

We are continuing with the preliminary engineering and discussions with equipment vendors necessary to place orders for the equipment required to comply with the staff position as clarified on pages 26 through 36 and Tables 2.1.8.6.2 and 2.1.8.b.3 of Enclosure 1 of your October 30, 1979, letter. We shall provide you with a schedule for the completion of the Category B requirements as soon as possible after the placement of purchase at which time the promised delivery dates of the equipment will be established.

Section 2.1.8(c) - Improved In-Plant Instrumentation Under Accident Conditions Procedures have been developed and implemented to accurately determine airborne iodine concentration in areas within the facility where plant personnel may be present during an accident. This wi'll be accomplished using portable iodine samplers equipped with silver zeolite cartridges. Counting shall be performed with a properly calibrated single channel analyzer or with a laboratory type multi channel analyzer. We are developing the capability to re=ove the sampling cartridge to a low background, low contamination area for further analysis in accordance with Clarification B to this staff position. This area will be either the Technical Support Center laboratory or a laboratory in a van to allow relocating the analyzer to a low background area. We plan to have this completed by January 1, 1981.

Containment Pressure Indication We are proceeding with the activities necessary to procure and install an extended range containment pressure monitor. This will require locating two pressure transmitters on column mounts. The two new pressure transmitters will be connected to existing containment instrument lines. One new indicator for each new pressure transmitter will be loacted on the main control board and one channel will also be recorded. We plan to have this instrumentation installed by January 1, 1981.

Containment Water Level Indication In order to provide continuous containment water level indication, the two existing level transmitters will be replaced. An additional unit similar to the others with a range of one foot will be added together with a stilling well. A new indicator will be located on the main control board for the narrow range level. A recorder will be added to record one of the wide range signals.

We are proceeding with the activities necessary to comply with this requirement by January 1, 1981.

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Discussion of Lessons Learned Short Term Requirements Page 7 Containment Hydrogen Indication The design approach to this modification will be to locate redundant hydrogen monitors near containment penetrations and to connect these monitors to the existing sampling lines which serve the hydrogen recombiners. The new sampling lines will tap off the existing lines between the containment pene-trations and the outside containment isolation valves. Because of this arrangement, the new sample lines will have electrically operated containment isolation valves.

Heat tracing will be provided on the new sampling lines to minimize condensation and to prevent solidification of boric acid in any entrained boric acid spray.

One new indicator for each hydrogen monitor will be added to the main control board with one channel being recorded. The indicators will cover-the range of 0 to 107. hydrogen. We are proceeding with the activities necessary to comply with this requirement by January 1, 1981.

Reactor Coolant System Venting We shall install a reactor coolant system head venting system. We plan to pursue the details of the design of the venting system necessary to comply with the additional design considerations provided in your October 30 letter and the development of procedures addressing the use of the vent system on a generic basis through the Westinghouse Group. The conceptual design is being reviewed and will be forwarded to the NRC upon completion of the review.

Section 2.2.1(a) - Shift Supervisor Responsibilities The Shift Supervisor's Responsibilities have been reviewed and a manage-ment directive was issued by the Vice President of Operations. This item is complete.

Section 2.2.l(b) - Shift Technical Advisor We shall provide on shift, at all times that average temperature of the reactor coolant system is greater than 200 F, an On-Shift Technical Adivsor.

This group of on-shift technical advisors shall have the responsibility for both accident assessment and an evaluation of operating experience. This review of operating experience will include a review of operating experiences at Beaver Valley as well as a review of abnormal operating experiences that occur at facilities of similar design which are brought to their attention through LERs, the Clearing House Reports or other means. Training will be completed by Janaury 1, 1981.

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Discussion of Lessons Learned Short Term Requirements Page 8 Section 2.2.1(c) - Shift and Relief Turnover Procedures We have reviewed and revised, in accordance with the staff position the procedures for shift and relief turnover.

Section 2.2.2(a) - Control Room Access Administrative Procedures that establish the authority and responsibility of the person in charge of the Control Room to limit access and administrative procedures that establish a clear line of authority and responsibility in the Control Room in the event of an emergency have been developed and implemented.

Section 2.2.2(b) - Onsite Technical Support Center A temporary Onsite Technical Support Center shall be established in accordance with the staff position as clarified in your October 30, 1979, letter prior to returning the unit to operation in mid-1980.

Our long range plan for. upgrading the technical support center to meet all requirements will be submitted by March 15, 1980. This delay in the submittal of the long range plan is required to allow enough time for the completion of a review of the habitability requirements and, if necessary, the selection of a suitable site for a permanent technical support center.

It is our goal to complete the installation of the permanent center, complete with necessary instrumentation and data transmission facilities by January 1, 1981.

Section 2.2.2(c) - Onsite Operation Support Center An onsite operational Support Center, in accordance with the requirements of the staff position, shall be established prior to returning the unit to operation in mid-1980. The area will be established in the Process Rack Room located below the Control Room. This area is on the same ventilation system as the Control Room.

Very truly yours, WAl' &

C. N. Dunn Vice President, Operations

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