ML20207P914
| ML20207P914 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/12/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM TAC-45114, NUDOCS 8701200401 | |
| Download: ML20207P914 (20) | |
Text
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Telephone (412) 393-6000 Nuclear Group InSppingpod PA150774 04
< S. Nuclear Regulatory Commission
} Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 NUREG-0737, Item II.F.2, ICC Instrumentation System Gentlemen:
By letter dated November 12,
- 1986, you requested additional information on our April 24, 1984 submittal describing the Inadequate Core Cooling Instrumentation (ICCI) system for Beaver Valley 1.
Attached is an update to our April 24, 1986 submittal along with a brief comparison of the Unit 1 and Unit 2 ICCI systems.
If you have any questions on this information, please contact my office.
Very truly yours,
)
/
J. D. Sieber Vice President, Nuclear cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Averi,
King of Prussia, PA 19406 Mr. Peter S. Tam U. S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
- Mail Stop 340 Director, Safety Evaluation & Control Virginia Electric & Power Company O"
P.O. Box 26666 D
One James River Plaza
)i Richmond, VA 23261 i
i 8701200401 B70112 PDR ADOCK 05000334 FA PDR
E N C L 0 S_U R E' I
Response to NRC Request for Information
. dated November 12, 1986 on Inadequate Cere Cooling Instrumentation I.
Update
-your
. April 1984 submittal' to reflect completed installations and design chcnges.
Response
A.
Completed Installations 1.
The RVLIS was completed and placed in service at'the fourth refueling outage.
2.
Modification of the Safety Parameter Display System
-(SPDS) to. include core exit thermocouple inputs has i
been completed as described in our April 24, 1984 submittal.
In
- addition, Train A'and B upper range, full range and dynamic head RVLIS level signals have j
been included as inputs to the SPDS and PVC computers.
2 3.
Preliminary work was begun during the fifth refueling.
outage on the Inadequate Core Cooling (ICC) upgrade of the core exit thermocouple system.
This consisted of environmental qualification splices of the thermo ouple cables at the containment penetration.
The final ICC 4
system upgrade will be completed at the 6th refueling outage scheduled for November 1987.
l B.
Proposed Upgrade The final configuration for the ICC monitoring system will i
be essentially as described in our April' 24, 1984 vubmittal with the following exceptions and clarifications.
1.
The current RVLIS microprocessor cabinet and associated Control Room plasma displays will be replaced with a Westinghouse ICC-86 monitor and displays.
The new ICC monitor consists of two
- sections, Train A
and B,
designed to electrical Class lE requirements.
The ICC monitor will functionally replace the
- RVLIS, the subcooling monitor and the current core exit thermocouple monitoring system.
Inputs to the ICC monitor will include the existing RVLIS inputs plus core exit thermocouple (CETC) and reference junction RTD
- inputs, as shown on the attached block diagram,
(
drawing ICC 668-1.
2.
The ICC monitor and displays will be powered from two separate Class lE power sources backed by the station i
The power source for Train A
and Train B
will be consistent with channel identification of the existing RVLIS Train A and B inputs.
L
- _ ~ _.......... _.... _. _. _. _... _.. _ _ _.. _ _ _ _. _.., _.. _.. -. _ _ _,
Encloture.I PEga 2 3.
The ICC. displays will be located in.the control room, as determined by human factors review.
Train A display will be located on the vertical board with a keypad on the benchboard.
Train B -will be installed in the location of the existing APDMS panel to the left of the control board.
4a.
The core exit thermocouple system will be. upgraded by replacing the thermocouple connectors at the reactor head with environmentally
. qualified.
connectors.
Environmentally qualified thermocouple extension cable will 1xn installed from the connectors to a
- new, environmentally qualified reference junction system inside containment.
At this point, EQ splices will be made to the existing copper thermocouple cables to the containment penetrations.
Use of the existing copper cable is based on EQ testing of originally installed BVPS-1 instrument cables.
b.
Outside containment, the thermocouple and reference junction RTD
- cables, which are now routed to.the existing thermocouple indicator, the plant computer, the SPDS and PVC computers, and the subcooling monitor, will be pulled back,.in part, and routed directly to the ICC monitor.
The thermocouple indicator, which is incompatible with the new (unheated) reference junction
- system, will be deleted.
The plant computer, SPDS and PVC computers will obtain CETC signals via isolated outputs from the. ICC monitor.
This configuration differs frcm that shown on Figure 1 of our April 24, 1984 submittal, which depicted the thermocouple signals branching off to other non-Class lE equipment without isolation.
This change in the proposed configuration 4
was made to achieve a greater degree of compliance with separation and independence
- criteria, and because of l
the possibility of. a computer malfunction that could load down the input, thus affecting the signals to the ICC monitor.
t c.
As noted in our April 24, 1984 submittal, the routing of the CETC cables will not fully satisfy the separation criteria of NUREG-0737 and Regulatory Guide 1.75 in the following respects.
Due to the i
configuration of the CETCs, Train A and Train B cables will be physically adjacent at the thermocouple columns exiting he reactor vessel head.
Separation of Train A and B
into separate raceways will begin at the closest practical location on the refueling deck.
From this point on, Train A
and Train B
thermocouple and
~
reference junction RTD cables will be routed in separate raceway.
- However, the existing neutral color-coded raceway routing will be utilized; therefore, the cables will be in raceway with other non-safety related cables.
Rerouting of the cables directly to the ICC monitor described previously, will eliminate Train A
and Train B common routing outside containment.
4
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Enclorurc I P gs 3 II. Provide a
brief description of the similarities and differences of the Unit 1 and 2 ICC designs.
Response
The following describes significant similarities and differences between the proposed Unit 1 ICC system and the Unit 2 system as described in submittals dated April 11, 1986 and July 31, 1986.
(Docket No. 50-412)
A.
Core Exit Thermocouple System 1.
Unit 1
core exit thermocouple system will be generally similar to the Unit 2 system in that there will be 51 thermocouples (26 Train A
and 25 Train B) with environmentally qualified reference junction systems.
Differences may exist in actual hardware description, since other manufacturers will be considered for the connectors, cable and reference junctions.
2.
Unit 1
will not utilize the Remote Processing Units (RPUs) described for Unit 2 and each display will read out only the thermocouples associated with that train.
Displays of all 51 thermocouples and the associated reference junction RTDs will be available on the non-1E SPDS, PVC and plant computers.
B.
Core Subcooling Margin 1.
Inputs for the core subcooling margin calculation will include:
Number of Channels Unit 1 Unit 2 Wide range RCS pressure 1 per train 3
Core exit thermocouples 26 Train A, 51 25 Train B Hot Leg Temperature 2 Train A, 1 Train B Reference junction RTD 2 per train 6
2.
For Unit 1, core subcooling will be calculated based on average of 5 hottest thermocouples per train for use in the emergency operating procedures.
Subcooling based on the hottest temperature will be displayed for information.
Subcooling margin calculation will also be performed in the SPDS and PVC computers.
I Enclosuro I Page 4 For Unit'2, core.subcooling will be. calculated based on auctioneered; high thermocouple quadrant-average' temperture.
3.
The RPUs described for Unit 2 will not be used in Unit-1, therefore,,each ICC microprocessor will.have inputs only from the sensors in its associ'ated train.:
C.
Reactor Vessel Level Instrumentation System 1.
The RVLIS inputs.for. Unit 1
are-similar.to Unit 2 except for the number of channels:
Number of Channels Unit 1 Unit 2 RCS hot leg wide range RTD 2 Train'A,
-2 1 Train B Wide range RCS pressure 1 per train 4
Differential pressure 6
6 Reference leg temperature 6 Train A, 12 7 Train B Reactor coolant pump status 6-4 2.
For Unit.
1, each plasma display will contain only one train of RVLIS information.
Train A RVLIS level.will be recorded on a 3-pen recorder.
Train A and B RVLIS signals will be input to the SPDS/PVC computer.
D.
' Displays-In Unit 2 the ICC instrumentation parameters are integrated into the Plant Safety Monitoring System which has two redundant seismically qualified flat panel displays, each capable of displaying all channels-of ICC-parameters.in addition to other plant safety parameters.
-For-Unit
'l the 'ICC parameters will be input to the Safety-Parameter' Display System and Plant Variable Computer via isolators from existing process instrumentation'and the new ICC. microprocessor.
These computers will be capable of displaying thermocouple core
- maps, subcooling margin and s
RVLIS levels.
Additionally, to meet the recommendation of NUREG-0737 for 1E powered backup CETC display, dedicated ICC displays will be installed.
Typical display pages for the Unit 1 ICC displays are provided as Attachments.
I' i
i
- i 1
Enclo;ura I l
Page 5 E.
Trend Capability Unit 2
has recorders for one train of RVLIS, one train of subcooling and one CETC channel.
The Unit 2 displays have the capability for 2-hour trend of CETC trisector maximum temperature, core subcooling margin, RVLIS level and RCP status.
Unit 1
has a
recorder for one train of RVLIS levels.
The ICC disp'.ay will trend average of 5 hottest thermocouples-per train for 30 minutes.
Other ICC parameters may be trended on the SPDS display for 30 minutes and the PVC display for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
F.
Alarm Capability The Unit 1
ICC displays will display alarm parameters in reverse video in a manner similar to that described for Unit 2.
For Unit 1
Alarms on the plant annunciator system will be provided for the following condition:
Low margin to saturation Core exit thermocouple average of 5 hottest CETC per train 1 1200*F.
RVLIS full range 40 and 5
hottest CETC average 1700*F with no RCP running.
ICC monitor malfunction.
III. Provide the projected implementation date for your ICCI including revised Technical Specifications.
A.
Installation of the ICCI upgrade is to be completed during our sixth refueling outage, tentatively scheduled to begin in November 1987.
B.
Technical Specifications for the sub-cooling
.aonitor are presently in place.
Technical Specificatiens for the upgrade will be submitted after installation, functional
,, testing is completed and the system is demonstrated operable.
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