ML20236B735
| ML20236B735 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/09/1989 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8903210254 | |
| Download: ML20236B735 (12) | |
Text
- - _ _ _ _ _ _ _
e-
[ ;j f er Valley Power Staten
$hippingport. PA 15077 0004 i
CEE*L.., c=
m oosm i
March 9, 1989 1
U.
S.
Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Proposed Operating License Change Request No. 22 Request for Additional Information Gentlemen:
1 Our letter dated January 30,
- 1989, submitted a
proposed license
- change, which involved licensing conditions 2.C.(7),
i 2.C.(8) and 2.C(9).
These items, as revised, will be required to be completed prior to start-up following the second BV-2 refueling outage.
On February 22, 1987, DLC discussed with members of your f
staff the specific items associated with the Detailed Control Room Design Review (DCRDR)
Condition 2.C.(8) and the Safety Parameter Display System (SPDS) Condition 2.C.(9).
l Attached is a
detailed description of the specific items associated with the DCRDR and the SPDS, which.DLC can not complete I
prior to start-up following the first BV-2 refueling outage.
As indicated in the license change request, and in discussions with your
- staff, substantial progress has been achieved with the 1
associated license condition items.
Also, we have determined that the few remaining items are enhancements that have no safety significance.
Very truly yours,
- b W
D.
Sieber Vice President Nuclear Group Attachments cc:
Mr. J.
Beall, Sr. Resident Inspector Mr. W.
T.
Russell, NRC Region I Administrator Mr.
P. Tam, Sr. Project Manager go(
'O i
8903210254 890309 PDR ADOCK 05000412 P
PDC g
_J
I l
License Condition No. 2.C.(8)
Detailed Control Room Design Review (DCRDR) l 2CIC-5514 - Digital Radiation Monitoring System (DRMS) Printout The Digital Radiation Monitoring System (DRMS)
"All Monitor Status" printout was designed for diagnostic use by Radcon only and is not used by the control room operators.
Operations Manual, Chapter 54, requires shift logging of the radiation monitor status which is taken from other DRMS displays.
Also, a status of all "OFF NORMAL" monitors is used during the board walkdown per OST 2.48.33.
This printout will not be revised as its use is not required by. Operations and the costs are excessive for obtaining i
i and revising the source code.
2MCR-0202 - Communications Console / Merge Switch We will install a
functional communication console in the Simulator.
The installation will accommodate a more detailed evaluation of the adequacy of the present location through training exercises.
This console is scheduled to be installed prior to start-up following the second BV-2 refueling outage.
2MCR-0203 - Walkie-Talkie Communications System j
l We will evaluate the operation of the walkie-talkie systems during the first BV-2 refueling outage.
The evaluation results will be factored into any design changes and scheduled to be complete before start-up following the second BV-2 refueling outage.
2MCR-0001 - Control Room Noise / Computer Fan Replacement /HVAC Improvements Study The HVAC study has been completed.
The feasibility of the recommended improvements concerning equipment and air-flow noise is being evaluated.
The specific noise areas being evaluated are the compressor, return air intake air
- flow, and air outlet diffuser.
All improvements will be scheduled to be completed prior to start-up following the second BV-2 refueling outage.
l 2MCR-0002 - Radiation Monitor System / Cabinet Fan Replacement We have determined that the RMS cabinet fans will not be replaced i
due to warranty concerns addressed by the vendor.
Engineering is evaluating the feasibility of applying sound absorbing material to j
the cabinet area to reduce noise.
Any resulting changes will be scheduled to be completed prior to start-up following the second BV-2 refueling outage.
2MCR-0008 and 0009 - HVAC System Air Flow Adjustments The HVAC system air flow balance will be re-evaluated following the completion of improvements resulting from the HVAC Study identified in 2MCR-0001.
Any required adjustments will be completed prior to start-up following the second BV-2 refueling outage.
1.
iicense Condition No. 2.C.(8)
Detailed Control Room Design Review (DCRDR)
Page 2 l
I 2MCR-0019, 2ES*-0020 & 2AB*-0021 - Emergency Lighting The emergency lighting conditions were previously tested and found to be
- adequate, i.e. at least 10-foot candles.
A subsequent test did not confirm the original test data.
We have determined that all required emergency actions in the control room and at the shutdown panels can be accomplished under the existing emergency light levels.
We will re-evalute the emergency lighting conditions in the control room and at the shutdown panels by obtaining additional illumination readings.
The additional measurements and required improvements, if any are identified, will be completed prior to start-up following the second BV-2 refueling outage.
2V**-2128 Annunciator " DARK BOARD" As indicated in the DCRDR Second Supplemental Summary Report, 23 annunciator windows were unnecessarily illuminated at that time and that an ongoing program would remain in-place to track progress until all problem windows had been resolved.
Of those 23
- windows, 2
windows have been cleared
- A8-4E and A8-5E Diesel Generator 2-1 (2-2).
The local panel Hi level setpoint has been I
raised.
Twelve (12) windows are scheduled to be cleared before start-up following the first refueling outage.
The following is a summary of the 9 remaining problem windows divided into 2 groups.
A.
Design changes to resolve the following problem windows are currently being engineered by DLC and will be scheduled for completion following start-up after the second BV-2 refueling outage.
1.
A4-7C - Loose Parts Monitor System Alarm A
change to inhibit the alarm during rod movement is being engineered.
The alarm will be inactive if the rods are being moved.
2.
A6-5F - Condenser Hotwell Level High/ Low This alarm has been functioning properly and has been clear;
- however, because of narrow operating band, the level alarm is frequent.
The instrument span will be changed to provide a
wider operating range and minimize nuisance alarms.
$1 cense Condition No. 2.C.(8)
Detailed Control Room Design Review (DCRDR)
Page 3 3.
A6-7H - Sixth Point Feedwater Heater Level High This alarm has been cleared; however, the high high and-the low high level instrumentation is: being raised to further minimize nuisance alarms.
4.
A8-6B - Heat Tracing System Trouble Two non-safety related panels are being removed as inputs to this window.(Condensate Polishing N1 & N2). Elimination of the condensate polishing panel inputs will reduce approximately 50%
of the alarm occurrences.
Every shift the operator is required to verify the status of all panels and for safety related
- panels, all-local panel alarms require verification upon occurrence.
The remaining alarms require a local response.
Additionally, for these
- panels, the control room annunciator will not-reflash. if a point is in alarm on the panel.
Surveillance of the non-safety related
- panels, once per shift,.is considered adequate verification of plant conditions..
5.
Al-4H - Service Water System Trouble The ' system is designed so that one pump is always idle.
When-the pump is
- idle, the pump seal water should be isolated to reduce system demand.
The. seal water isolation alarm point is currently not interlocked to pump operation.
A design change scheduled for completion prior to start-up following the second BV-2 refueling. outage will establish this interlock.
A procedure'for starting.
the pump currently directs the operator to establish the seal water alignment.
1 6.
A4-3D - NIS Source Range Flux Doubling.
This alarm functions properly.
When starting up the unit, the fuses are pulled when operation is beyond the source range.
This is to avoid an inadvertent energization of the source range detectors.
We have experienced a BV-1 unit trip as a
result of the system design.
Procedures are in place to direct the operator to install the fuses after a
plant shutdown and to remove the fuses during i
operation when operating beyond the source range.
A design change will be implemented after start-up following l
the first refueling outage.
)
l L_______________---_____
e ficense Condition No. 2.C.(8)
Detailed. Control Room Design Review (DCRDR)
Page 4 7.
A4-5A
- Digital Radiation Monitoring System (DRMS) Trouble This annunciator is illuminated because the-following monitor channels are on standby and only-in service when there'is process flow:
2SGC-RQIl00 Liquid Waste Effluent Monitor 2CNA-RQIl00 Auxiliary Steam Condenser Monitor 2CNA-RQIl01 Evaporator Reboiler Condenser Monitor 2SWS*RQIl00A,B,C,D Recirc Spray Heat Exchanger Monitors 2HVS*RQ109C (Airborne) Elevated Release Mid Range Detector l
2HVS*RQ109D (Airborne) Elevated Release High Range Detector The pumps on these monitors are normally not running therefore, a loss of flow signal is generated resulting in the system trouble signal.
If another channel experiences trouble and a trouble alarm is initiated, the annunciator will reflash and require operator acknowledgment.
A design change has been initiated to modify the DRMS software to inhibit the loss of flow alarm when a pump i
running signal has not been received.- This change will be completed before start-up following the second refueling l
outage.
The alarm status of the monitors do not change l
l when the channel is placed in standby.
Additionally, the operator is required to review and log the monitor status j
on a shift basis to maintain an awareness of the radiation monitors status.
B.
Design changes are not planned at this time for the following annunciators for the reasons provided:
1.
A2-1A - Steam Generator Blowdown System Trouble This annunciator receives approximately 42 inputs from both trains.
Both evaporators are not operated at the same time and all of the alarm' points associated with each train are not interlocked to train operation.
The knife l
switches are pulled for some of the points to reduce the l
quantity of points being displayed on the annunciator CRT.
The procedure to start-up the evaporator directs the operator to activate the points during start-up.
A very costly design change would be required to completely eliminate this nuisance alarm.
The design change will not be implemented.
The annunciator has reflash capability for new points coming into alarm and the CRT identifies cleared points therefore, the operator is aware of the system conditions and alarm status.
, License Condition No. 2.C.(8)
Detailed Control Room Design Review-(DCRDR)
~
Page 5 2.
A2-lD - Nitrogen Supply Header Pressure Low This alarm is initiated by one low pressure switch'in the supply' header.
The supply-valves are periodically closed because of small. leaks.
This results in a low pressure alarm.
Station maintenance will continue to repair leaks;-
- however, to prevent unnecessary depletion of the nitrogen
- supply, the system supply valves will be required to be periodically closed.
Operations is aware of the system status -and the illuminated window alerts the operator to a low pressure condition.
Operators have time to open the supply valves in the event that the nitrogen is required for any supplied componer.t.
l l
I i
l 1
License Condition No. 2.C.9 Safety Parameter Display System (SPDS)
Field input verification testing activities (SSER-6 Section 18. 2. 2.1 ( 4 ) )
have been completed;
- however, deficiencies were identified with various SPDS field inputs.
The following discussion identifies the SPDS field input requirements, the field input descriptions, and DLC's plans to resolve the deficiencies.
1.
2FPW*AOV204 -
Rx Containment Charcoal Filter System Deluge Isolation Valve 2FPW*AOV205 -
Rx Containment Deluge System Isolation Valve 2FPW*AOV206 -
Rx Containment Hose Racks Isolation Valve 2FPW*AOV221 -
Rx Containment Charcoal Filter System Deluge j
Isolation Valve These four fire protection valves are Phase A containment isolation components identified in WCAP-10170 Appendix C-S1.
We have added Containment Isolation Status in response to an NRC concern identified in SSER-6 18.2.2.2(7).
The closed /not closed status of these valves is not individually displayed but does input to the containment Isolation Calculation which is displayed on the overall plant status display 2 PSI.
Field input verification testing has identified the above valves to be wired incorrectly.
The valve position indication is,
- however, available to the operator at the Main Control Board.
An engineering change has been initiated to correct the closed /not closed field input of these valves to the SPDS.
This change is scheduled to be complete before start-up after the second BV-2 refueling outage.
2.
2 MSS *AOV101A,B & C - Main Steam Isolation / Bypass Valve Position The position status (open/ intermediate / closed) for these valves is required per WCAP-10170 Appendix C-S1.
These valves appear on the Main Steam System Display 3MS1.
Field input verificaiton testing has determined that the valves are currently wired to provide the open/not open indication.
- However, the closed /not closed field input status is not provided.
An engineering change has been initiated to include the closed /not closed field input status of these valves on the SPDS.
This change is scheduled to be completed before start-up after the second refueling outage.
The position indication of these valves is available on the main control board at the control switches
1-l:
4p -
License Condition No.
2..C.9
-Safety Parameter Display System (SPDS)
Page 2 l
l l
3.
2 SIS *MOV863A & B - LHSI Pump Discharge Valves 2 SIS *MOV8887A & B - LHSI Pump Discharge to Hot Legs 2 SIS *MOV-8811A & B - RSS Pump Discharge to Safety Injection Header the open/ intermediate / closed position status of these valves l
is included in WCAP-10170 Appendix C-S1 and required to be i
displayed on the SPDS Low / Intermediate Safety Injection Status Display 3SI2.
Field input verification testing has identified the above valves.to be wired incorrectly by not properly indicating closed /not closed.
The position indication of l
these valves is available on the main control board.
An engineering change has been initiated to correct the closed /not closed field input status.
This change is scheduled to be completed before start-up following the second BV-2 refueling outage.
1 4.
TV-1, 2,
3 & 4 - Turbine Trip Valves i
The closed /not closed indication of the turbine trip valves are currently included on the SPDS Main Steam System Display 3MS1.
WCAP 10170 Appendix C-S1 does not require that the SPDS display position status of these valves.
Engineering has l
determined that the additional wiring required to provide i
these inputs to the SPDS would be very costly.
The trip valve status inputs will be disabled from the SPDS.
The position indication of these valves is available on the main control
{
board.
I 5.
2QSS*P24A&B - Chemical Injection Pumps l
The start /stop status indication for these pumps is required to be verified by the operators as part of the Containment Isolation Phase B
Checklist per EOP E-0.
- However, the operation of these pumps does not represent containment isolation valve status.
In response to an open item addressed in SSER-6 Section 18.2.2.2(7),
we added the containment isolation phase A
and phase B status indication to the SPDS Plant Status Display 2PSl.
The EOP check lists were used to verify the parameter requirements.
Additionally, the Chemical Injection pumps were added to the Containment Quench Display 3CSI.
Field input verification testing has determined that j
the start /stop status inputs are not wired.
Engineering has
)
determined that the additional wiring required to provide l
these inputs to the SPDS would result in excessive costs.
The l
pump start /stop status input will be disabled from the SPDS.
l The operation of these pumps can be verified by monitoring the
{
chemical addition tank level which is provided on SPDS
)
Containment Quench Display 3CS1.
Status of the pumps is i
provided in the control room.
l
License Condition No. 2.C.9 Safety Parameter Display System (SPDS)
Page 3 As indicated in our conversation of February 22, 1989, the Site Acceptance Testing (SAT) and system response time testing are not expected to be completed prior to start-up following the first BV-2 refueling outage.
Site acceptance testing of the ERF Computer System SPDS function has been conducted.
Initial time response testing was submitted under previous cover.
Subsequent engineering evaluation of our time response testing concluded that response time meets regulatory requirements.
Additional
- testing, including time response
- testing, will be required following resolution of some system faults to provide assurance that existing time response does not deteriorate.
A description of the currently outstanding faults is provided below.
VISTA Display Generator 173 -
VISTA is not a console function 176 -
VISTA not functioning per instruction manual.
309 -
VISTA save and update functions lock up.
Three faults are associated with the VISTA graphic display creation function of the ERFCS/SPDS Computer.
These faults do not affect the operation of the SPDS and the current SPDS displays agree with the design specification.
System Faults 47 -
Response Time to complete a display ERFCS idle time goes to zero %, contract specification 228 requires 20%
Although these faults represent a specification deficiency, under normal operating conditions, the system operates properly and the system response times satisfy the regulatory guidelines of NUREG-0700 to which the system was evaluated. We are investigating methods to minimize the possibility of system overload by restricting access to unnecessary functions at certain terminals.
These functions include
- HDSR, VISTA and logging.
These improvements and the elimination of 2 Alternate Technical Support Center consoles will reduce loading and should result in improved j
system response.
{
t
Licenso Condition No. 2.C.9 Safety Parameter Display System (SPDS)
Page 4 Digital Radiation Monitoring System Inputs 244 -
DRMS standby effluent monitor status 379 -
DRMS Monitor off-line status i
The SPDS receives information from the DRMS.
Under normal conditions, the SPDS intermittently receives incorrect DRMS data quality which causes the SPDS to display incorrect quality code information.
This is discussed under this cover on CRDR, page 4, Dark Board A4-5A.
- Also, the DRMS read time is specified to be five seconds but due to DRMS processing, a 20 second read time is required to overcome the DRMS processing deficiencies.
A design change to the DRMS is scheduled to resolve Dark Board Annunciator A4-5A prior to start-up following the second BV-2 refueling outage.
The DRMS monitor off-line status solutions are being evaluated for implementation prior to start-up following the second BV-2 refueling outage.
138 -
Deletion of communication processor The communication processor equipment was provided by the vendor but the equipment is not used.
This fault does not affect SPDS displayed information but is a discrepancy.
This equipment will be removed from the equipment specification and the testing requirements will be removed from the Site Acceptance Test.
I Display Related Faults 383 -
Device Status Function Lockup The lockup of the device status function can only occur when an invalid request is made in combination with a sequence of key depressions.
The cursor will disappear locking up the screen.
Escape from the locked-up screen requires only the depression of any function key.
This fault does not affect SPDS displayed information.
"t.
4 in
/
(k 2.C.9 Licansa Condition No.
Safety Parameter Display System (SPDS)
-Page 5-i i
Point Processing Faults 1
Digital Rod Position Indication (DRPI) Rod Calibration
-223 This fault will be addressed during the first BV-2 refueling outage when the rods can be moved.
j 225 -
ERFCS vs Plant Computer System - Time clock disagreement Digital point times do not agree between the ERFCS and PCS.
This is due to machine processing characteristics which are different.
This is a discrepancy that does not affect the SPDS.
297 -
ANIN Analog Point Details l
Color inconsistencies have been identified between the i
SPDS displays and the Point Details for Poor Data quality-only.
The point details are displayed using the ERFCS
+
quality code which may differ from the SPDS.
We are evaluating this condition to determine whether or not a software change can establish consistency or operator training will be required.
343 -
Multiple Trouble Light Annunciator (TLA) Pushbutton Inputs The point summaries on the ERFCS do not contain a report ~
j to display multiple TLA alarms.
This fault does not i
affect SPDS displayed information, f
359 -
Communication Failure Test
'j This test is an ERFCS diagnostic test only and is not an SPDS display related problem.
Four State Descriptor switch on/off 377 I
This fault relates to code that is missing from the four state descriptor point type for maintaining printer control.
This fault reflects a discrepancy in accordance with the specification.
This fault does not affect SPDS i
displayed information.
DMUX Message 382 1
This fault is an ERFCS diagnostic function only and does not affect SPDS displayed information.
- a. ;,'.'
License-Condition No. 2.C.9 Safety Parameter Display System'(SPDS).
Page 6 Documentation Related Faults 287 -
Demand Performance Calculations 1
362 -
Daylight Saving Time Documentation Fault 362 does not affect the.SPDS displayed information because date and time is received from the PSMS.
Demand.
performance calculations code is deficient and does not affect l
SPDS displayed information.
I Logging Faults 331 -
Logging functions are interspersed with alarms on the Operations-Journal Printer The logging function is associated with the'offline status of the primary printer.
The resolution to this fault is considered i
to be an enhancement and does not affect SPDS displayed information.
i l
These system' capabilities, associated with the above faults, do not adversely affect the performance of the SPDS or the accuracy and reliability of the SPDS displayed information.
The Site-Acceptance Test and final response time testing are scheduled to be completed prior to start-up following the second BVPS-2 refueling outage.
1
'