ML18149A074
| ML18149A074 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/31/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Rubenstein L Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18130A413 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 86-171, NUDOCS 8604070130 | |
| Download: ML18149A074 (23) | |
Text
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 W. L. STEWART VxcE PRESIDENT NUCLEAR 0PERATXONS Mr. Harold R. Denton, Director March 31, 1986 Office of Nuclear Reactor Regulation Attn: Mr~Lester S. Rubenstein, Director PWR Project Directorate No. 2 Division of PWR Licensing - A U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1&2 CONTROL ROOM DESIGN REVIEW FINAL
SUMMARY
REPORT Serial No.86-171 E&C/TLG/hts:6321C Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 As delineated in our Control Room Design Review (CRDR) Program Plan submitted to you in accordance with NUREG-0737 Supplement 1 on March 1, 1984, Serial No. 087, and as revised by the comments provided to us in the Results of In-Progress Audit on January 8, 1985, we have performed a human factors engineering review of the Surry Power Station Units 1&2 Control Room.
Enclosed is (1) our Final Summary Report, Volumes 1&2, documenting the approach, the process and the results of this review and (2) our Proposed Corrective Actions and Implementation Schedule, Attachment I, defining the proposed corrective actions to be taken as a result of the program.
Selection of the proposed corrective actions was a complex process that considered the inter-relationship with and between other ongoing Virginia Electric and Power Company programs, such as installation of a Safety Parameter Display System, operator training, instrument upgrade per Regulatory Guide 1.97, Emergency Operating Procedures Revision 1 upgrades, plant process computer replacement, etc.
In addition, those corrective actions determined to be 11safety significant 11 were reviewed for cost effectiveness and feasibility of installation on a conceptual design basis. The result of this review is the list of proposed corrective actions provided in Table FSR-1 of Attachment I to this letter. However, if during the development of the detailed design it is determined that a proposed corrective action is not cost effective or feasible as originally believed, it may become necessary to develop alternative corrective actions. These alternative corrective actions will be reviewed and assessed in accordance with the Nuclear Design Control Program, which incorporates the same guidelines used in our CRDR review process.
---8604070130 860331-~-.
PDR ADOCK 05000280 '
p PDR 61-TLG-6321C-1
Mr. Harold R. Denton Please note that the proposed corrective actions identified in Table FSR-1 of Attachment I are for the "safety significance" HEDs and that no corrective actions are included for HEDs without "safety significance." Potential corrective actions for HEDs without "safety significance" were identified by the CRDR Project Team and can be found in Volume 2 of our Final Summary Report.
These potential corrective actions will be reviewed as part of the normal Virginia Electric and Power Company program for plant improvements.
10t~~*
W. L. Stewart Attachments
- 1)
Proposed Corrective Actions and Implementation Schedule, Attachment I (6 copies)
- 2)
Final Summary Report (6 sets - 2 Volumes/set) cc:
Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station 61-TLG-6321C-2 2
INTRODUCTION CONTROL ROOM DESIGN REVIEW FINAL
SUMMARY
REPORT SURRY POWER STATION UNITS 1 & 2 ATTACHMENT I SERIAL NO.86-171 The object of the review and assessment phases of the Control Room Design Review (CRDR) was to identify ways to "improve the ability of the nuclear power plant operator, to prevent or cope with accidents if they occur by improving the information provided to them." This process involved collection, reduction and analysis of data pertaining to the adequacy of the control room design from a human factors perspective. This was followed by an assessment of the human engineering discrepancies (HEDs) identified in the process.
REVIEW PHASE The review phase of the CRDR was comprised of the following four activities discussed in the Final Summary Report (FSR), Volume 1:
- 1. A review of normal, abnormal and emergency operations experience through interviews and document reviews (FSR Chapter 2).
- 2.
A control room survey associated with normal, abnormal and emergency operations to identify deviations from human factors principles (FSR Chapter 3).
61-TLG-12008-1
- 3.
A system functions review and task analysis of emergency operations
( FSR Chapter 4).
- 4.
A task verification and validation of emergency operations (FSR Chapter 4).
ASSESSMENT PHASE The assessment phase of the CRDR was comprised of the following three activities discussed in Chapter 5 of the Final Summary Report, Volume 1:
- 1.
Review and confirmation of the HED.
- 2.
Assessment of the HED against three criteria: the potential for error, the consequences of error and the safety importance.
- 3.
Assignment of a category/priority rating to the HED.
The individual HEDs were organized into the following three groupings by category and priority as follows:
Group A - 3/3 criteria were judged high Group B - 2/3 criteria were judged high Group C - 1/3 criteria were judged high 61-TLG-1200B-2
e REVIEW OF SAFETY SIGNIFICANT HEDS AND THE IDENTIFICATION OF THEIR PROPOSED CORRECTIVE ACTIONS Within each category/priority group the HEDs with common potential corrective actions were collected.
The potential corrective actions for the Group 1A1 HEDs and Group 18 1 HEDs with high safety importance were identified as the HEDs with 11 safety significance 11
- Both Engineering and Operations Management reviewed the potential corrective actions for these safety significant HEDs.
These reviews included preliminary feasibility studies, preparation of budgetary cost estimates and cost-effective evaluations.
In cases where Management's review took exception to the HED Assessment Team disposition for a HED, the HED was returned to the Team for their review and approval.
These reviews resulted into the proposed corrective actions listed in Table FSR-1 of this Attachment.
Table FSR-1, provides a description of the proposed corrective action, along with the associated HEDs which are addressed by that action. Justification is provided where the proposed corrective action is anticipated not to fully correct the HEDs.
However, in some cases, the extent to which a corrective action will fully correct an individual HED within a grouping cannot be determined until the development of the final engineering design.
The proposed corrective actions in Table FSR-1 identify the current scope.
61-TLG-1200B-3
e IMPLEMENTATION PLAN The proposed corrective actions for HEDs with "safety significance" fall into five implementation categories:
immediate, short term, long term, normal program and no action.
Immediate (I) Corrective Actions (0-2 Years)
Thirty-one (31) proposed corrective actions were identified for HEDs which could be corrected by simple enhancements, procedure revisions and/or training. There were also some extensive corrective actions that have been incorporated into design changes that were in progress for other programs.
At this time, the majority of these immediate corrective actions are in progress or complete.
Short Term (ST) Corrective Actions (0-4 years)
Thirty-three (33) proposed corrective actions were identified for HEDs which could be corrected by short term actions (enhancements, major procedure revisions, and design changes).
Long Term (LT) Corrective Actions (0-8 years)
Two (2) proposed corrective actions were identified for HEDs to be corrected by complex or interrelated design changes.
The exact scope of these changes is dependent upon the development of design alternatives and 61-TLG-1200B-4
e further evaluation of the impact of design changes associated with other programs (e.g. R. G. 1.97, SPDS, computer upgrade, etc.).
Normal Program (NP)
Sixteen (16) proposed corrective actions were identified that were not cost-effective and/or required space that is not available under current conditions.
These corrective actions could become cost-effective and implemented at a later date if the need arises for a design change in the same area or on the same equipment or if the necessary space becomes available.
No Action Four (4) proposed corrective actions were identified for HEDs with "safety significance" where there is no feasible or cost-effective corrective action.
In these cases, a justification is provided.
These changes could possibly be made given the freedom of a new plant design, but the constraints.of existing equipment in an operating plant make the costs of a corrective action high compared to the potential benefits.
SUMMARY
The final implementation schedule for individual proposed corrective actions will vary with the availability of resources (including work time and space in the control room) and the complexity of the final corrective action. Table 61-TLG-1200B-5
e FSR-1 provides a summary of the safety significant HEDs with the proposed corrective actions and proposed implementation schedules.
Please note that as specified in Paragraph g, Section 5.2 of Supplement 1 to NUREG 0737, the scheduled durations identified in Table FSR-1 will begin after the NRC has issued an SER and any open issues are resolved.
61-TLG-12008-6 I
PROPOSED CORRECTIVE ACTION RESPONSIBILITY I
ENGINEERING DESIGN CHANGE NON-DESIGN CHANGE (OPERATIONS)
TRAINING TOTAL TABLE FSR-1 CONTROL ROOM DESIGN REVIEWS FINAL
SUMMARY
REPORT SURRY POWER STATION UNITS 1 AND 2 SUftlt1ARY OF PROPOSED CORRECTIVE ACTIONS AND IMPLEMENTATION SCHEDULE I
PROPOSED IMPLEMENTATION SCHEDULE
( 0-2 yrs)
( 0-4 yrs)
. LT (0-8 yrs) 7 31 2
19 2
6 32 33 2
1 Total number of Corrective Actions per listing is 83 while, the total number ATTACHMENT 1 TABLE FSR-1 SERIAL NO.86-171 NP No 14 3
2 16 3
of Corrective Actions listed in Summary is 86, 3 greater than the listing, due to the split implementation times on study-type Corrective Actions.
61-TLG-2148B e
Total 57 23 6
861
CORRECTIVE ACTION #
CAlE CA2E CA3N CA4E CA5E TABLE FSR-1 CONTROL ROOM DESIGN REVIEW FINAL
SUMMARY
REPORT SURRY POWER STATION UNITS 1 AND 2 ATTACHMENT I TABLE FSR-1 SERIAL NO.86-171 PROPOSED CORRECTIVE ACTIONS AND IMPLEMENTATION SCHEDULE PROPOSED CORRECTIVE ACTION To address high ambient noise in control room; limit access to Control Room on day shift, distribute lower powered speakers strategically, and investigate alternative noise reduction techniques.
Resurvey control room.
Coordinate with CA73E.
Provide meter for total Auxiliary Feed-water Flow (0-1500 GPM}.
Coordinate with CA11E.
Emphasize in training that all controllers indicate demand not position.
Provide RED/GREEN lights on benchboard for Reactor Trip Breaker Status.
Existing Core Cooling Monitors to be replaced by Integrated Core Cooling System.
I I
ASSOCIATED HEDS 20000011 20000004 20000010 20000012 20A00209 22A00210 20002018 20001104 22A02029 22A03041 20001107 20A01136 20A02205 23001224 22A02047 22A02048 20A02233 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED 45-TLG-2147B/rev. k-1 e
CORRECTIVE ASSOCIATED JUSTIFICATION FOR PARTIAL OR ACTION #
PROPOSED CORRECTIVE ACTION SCHEDULE HEDS NON-CORRECTION OF HED CA6E Demarcate and add colored background on ST 20A01305 Auxiliary Shutdown Panel same as MCB.
Tape is to be removed and replaced with orange and purple color dots on labels. Coordinate with CA21E and CA24E.
CA7T Train operators to go to Radiation Monitor.
I 20A02015 trend recorders for trend information and to Radiation Monitor meters for current values.
CAST Scale to pen relationship has been coded I
20A02016 on multiscale meters.
Initiate job per-formance measures (JPM) on reading of multiscale meters.
CA9E Provide Pressurizer Spray Valve position ST 20A02045 indication with RED/GREEN Lights.
22A03206 45-TLG-2147B/rev. k-2
CORRECTIVE ACTION #
CAlOE PROPOSED CORRECTIVE ACTION Perform study of Annunciator Alarm System and implement upgrades as necessary.
45-TLG-21478/rev. k-3 SCHEDULE ST/LT ASSOCIATED HEDS 20A02106 20002120 20002121 20002122 20A02101 20A02102 20A02906 20A02103 20A02119 20A02125 20A02903 22A02302 20803005 22A02110 22A02111 22A02112 22A02114 22A02115 22A02116 22A02123 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED Additional study of the Annunciator Alarm System is required due to the complexity and variety of its problems.
Also, timing and integration of the corrective actions for the alarm system must consider the impact of the installation of the SPDS computer and the planned upgrade of the plae process computer.
CORRECTIVE ACTION #
CAllE CA12E CA13N CA14E CA15E CA16T PROPOSED CORRECTIVE ACTION Rescale auxiliary feedwater flow indicators (linear, 0-500 GPM-increments of 10 GPM)
Coordinate with CA2E.
Redesign Permissive Status Lights to ensure consistency in terms of messages, illumination sequence, location and arrangement.
Periodic tests will be performed in accordance with PT-26.1 to verify operation of Radiation Sampler filter light.
Replace Reserve Station Transfer control switch handles to minimize inadvertent operation.
Rearrange EOG #3 panels to be similar to EOG #1 and EOG #2 and label accordingly.
Coordinate with CA23E and CA75E.
Investigate difficult to operate controls for any maintenance problems.
Emphasize use of manual controls during training using job performance measures (JPM).
45-TLG-2147B/rev. k-4 SCHEDULE ST LT I
I ST I
ASSOCIATED HEDS 20A02216 20A02230 23002243 20A02303 20A02315 22A02308 20A01313 20A02307 20A03007 22A03037 20B23029 20A03033 20A03013 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED No guards are to be provided for these control switches since:
(a) no inadvertent operation has ever occurred in twelve plus years of operation (b) exist-ing annunication would inform opera-tor if inadvertent operation occurred (c) these control switches, with ~
exception of the Reserve Station
~
Transfer whose handles are being replaced, are redundant trains of which only one could be inadvertently operated.
CORRECTIVE ACTION #
CA17E CA18E CA19E CA20N CA21E CA22E CA23E CA24E PROPOSED CORRECTIVE ACTION Change flow indication for eves Charging and Letdown (linear 0-300 GPM).
Change existing annunciator for Safety Injection actuation to Train 11A 11 actuation only.
Add new annunciator for Train 118 11 Safety Injection actuation.
Rewire Pressurizer Heater Control switches so that RED light is not defeated when switch is in pull-to-lock position and green light is extinguished.
Ensure enforcement of standing order that controls use and placement of temporary labels (operator aids).
Provide correct lenses as required on Auxiliary Shutdown Panel to meet green/
amber/red convention.
Coordinate with CA6E and CA24E..
Remove unnecessary indicating lights from Heat Tracing Panel.
Modify EOG Megawatt, Megavar and RPM indication on EOG panels to improve viewing.
Coordinate with CA15E and CA75E.
Determine displays that most significantly affect plant safety on Auxiliary Shutdown Panel and modify to improve viewing.
Coordinate with CA6E and CA21E.
45-TLG-2147B/rev. k-5 SCHEDULE ST ST ST I
ST NP ST ST ASSOCIATED HEDS 20A03405 20A02214 20A03406 20B12305 22A01147 22001139 22A01141 22A01150 22A01151 22A01308 22A02086 22A02314 22A02088 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED Switch handle change is not requi~.
Possible error in response is a function of incorrect information provided by status lights, not operation of wrong equipment.
Relocation of secondary side plant controls is not necessary to ensure plant safety and is not cost beneficial.
CORRECTIVE ASSOCIATED JUSTIFICATION FOR PARTIAL OR ACTION #
PROPOSED CORRECTIVE ACTION SCHEDULE HEDS NON-CORRECTION OF HED CA25E Provide direct pressurizer PORV position I
23001207 indication with RED/GREEN status lights.
CA26E Provide better functional arrangement of 23001223 Containment Sump Level indicators Coordi-nate with CA48E.
CA27E Provide better functional arrangement ST 23001225 of SI and CLS controls.
CA28N Ensure that Annunciator Response Procedure I
23A02917 instructs Operators to reset the Pressur-izer Safety Valves annunciator.
CA29E Perform study to identify methods to ST 20000009 correct control room glare/lighting 20000008 problems and implement improvements.
20000001 20000003 20000014 CA30N Label RCS Pressurizer Pressure Recorder I
20001106 Readings.
CA31E Provide Reactor Coolant System (RCS)
I 20001220 e
23B01001 45-TLG-2147B/rev. k-6
CORRECTIVE ACTION #
CA32E CA33N CA34T CA35T CA36E CA37E PROPOSED CORRECTIVE ACTION SCHEDULE Add RCS WR pressure to left benchboard No in RCS System Controls area (0-3000 PSIG).
Initiate Job Performance Measure for Operators on setting of Hagan Process Controllers.
Train Operators in correlation of recorder output to display output.
Emphasize log scale reading in training.
Redesign Auxiliary Ventilation Panel.
Consolidate indication and controls for common ventilation equipment on single board and provide mimic.
Relocate cables to the PAMS panel and remove ramp which covers them.
I I
I
'NP No 45-TLG-21478/rev. k-7 ASSOCIATED HEDS 20001221 23801001 20002010 20002011 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED Addition of RCS wide-range pressure indication is not feasible due to physical limitations (interferences with terminal blocks, board structural/seismic steel and available space).
No qualified recorders available to fit into A
limited space. This indication is~
already provided on SPDS computer and is located on left vertical board.
20002012 20003016 20A01215 20A03209
~
23003019 22A01310.
22A03215 22F23026 20A00114 The cables cannot be routed under the floor to eliminate the ramp because of interferences with column and steel, preventing core drilling. The ramp was required for installation.
CORRECTIVE ACTION #
CA38E PROPOSED CORRECTIVE ACTION
. Perform Labeling study to determine labeling needs and concerns of Operations.
Relabel boards to 0700 guidelines.
45-TLG-21478/rev. k-8 SCHEDULE ST ASSOCIATED HEDS 20A01101 20A01143 20A01148 22A01108 22A01126 22A01133 22A01149 20A01311 22A01109 22A01110 22A01111 22A01129 22A01137 22A03101 22A01112 22A01114 22A01120 22A01130 22A01145 23A01006 22A01122 22A01123 22A01124 22A01132 22A01146 20A02042 22A01144 22A01301 22A01304 22A02311 22A02313 23A03210 23A03213 20A02017 22A02603 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED
CORRECTIVE ACTION #
CA39E CA40N CA41E CA42E CA43E CA44E CA45E CA46E PROPOSED CORRECTIVE ACTION Selectively investigate for Lamp T~st capability, any safety systems with legend lights that have single bulbs and that are not normally illuminated.
Change RED light on Unit 2 EOG to YELLOW light for 11 EMERG GEN #2 TRIP AUX RESET BUTTON 11 Provide visual displays and indications missing from control room primary area.
Provide expanded scale for Chemical Addition Tank Level on RWST Recorder.
Provide valve position indication on flow controllers with RED/GREEN lights.
Provide larger scales on Vent Air Flow Indicator and Vent Stack Flow Indicator.
Increase scale range to accommodate
{maximum) flow.
If feasible, tilt indicators forward to improve reading.
Change Condenser Vacuum indication scale
{20~30 inches Hg VAC).
Perform study to determine scale
. requirement for Boron Recovery Primary Drain Tank Pressure and implement.
45-TLG-2147B/rev. k-9 SCHEDULE ST.
I NP NP NP NP NP ST/NP ASSOCIATED HEDS 20A01216 20A01316 20A02005 20A02052 22A02027 20A02210 22A02070 20A02035 22A03216 20A02050 20A02036 22A02073 20A02202 20A02913 22A02078 20A02204 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED e
l I
CORRECTIVE ASSOCIATED JUSTIFICATION FOR PARTIAL OR ACTION #
PROPOSED CORRECTIVE ACTION SCHEDULE HEDS NON-CORRECTION OF HED CA47N On Boric Acid Storage Tank level indication I
20A02215 mark scale face with Tech. Spec. limit and alarm setpoint.
CA48E Rescale Recirc Spray Sump Level Indication I
20A02236
{2 inch increments) and put markings on 22A02060 scale as necessary. Coordinate with CA26E.
CA49N Rescale Containment Sump Level Indication (0 to 25 inches with 5 11 major increments I
20A02241 and 1 11 minors).
CASON Replace scratched glass and remove legends I/NP 20A02402 from trend recorder windows.
Coordinate with CA51N.
CA51N Replace trend recorder continuous flow ST 20A02403 pens with felt tip cartridges, as required.
20A02410 23A02415 CA52N Implement Preventive Maintenance Program I
20A02404 for trend recorders. Coordinate with CA49N.
CA53E Provide permanent installation of SG Level NP 20A02414 Narrow Range trend recorder on bench board 22A02082 near Feedwate~ Control station.
CA54E Perform studies to change setpoints, as NP 20A02904 necessary, on nuisance alarms in Control Room.
CA55E Make control switches for the steam supply ST 20A03011 Relocation1 of switch not necessary.
to the Steam Driven Aux Feedwater Pumps the Switches are redundant train~ of same as other valve control switch.
which either one can initiate pump
.. ~
operation.
45-TLG-2147B/rev. k-10
CORRECTIVE.
ASSOCIATED JUSTIFICATION FOR PARTIAL OR ACTION #
PROPOSED CORRECTIVE ACTION SCHEDULE HEDS NON-CORRECTION OF HED CA56E Rearrangement of Charging Pump MOV NP 20A03031 Not necessary to relocate or controls to be more functionally arranged.
rearrange valve controls to benchboard.
Valves are utilize for maintenance purposes only.
CA57E Provide switch guards for Condenser I
20A03039 Circulation Water Inlet Valves with clear flip-up covers.
CA58E Provide switch guards for Main Steam Trip I
20A03051 Valves with clear flip-up covers.
CA59E Relocate Annunciator pushbutton controls ST 20A03069 on benchboards for ease of access.
23003052 CA60E Investigate rewiring of existing status lights on Auxiliary Feedwater Pump Control Switches to extinguish in pull-to-lock ST 20B22306 position and the desireability of adding a 4th (white) status light.
CA61E Rearrange Accumulator Test Line Isolation ST 20Vl3022 Valves control switches. Coordinate with 20003017 CA74~.
CA62N Rewrite list of abbreviations/acronyms to I
22A01302 include a 11 abbreviations/acronyms used on labels, annunciators, legends.
CA63N Add zone markings to level indication for I
22A01704 Accumulator Tanks.
CA64N Add an intermediate graduations (heavier I
22A02023 line) for each value bf 10 on pressure indication for the Containment Leakage
- Monitoring System.
45-TLG-2147B/rev. k-11
CORRECTIVE ACTION #
CA65E CA66E CA67N CA68N CA69E CA70E CA71E CA72E PROPOSED CORRECTIVE ACTION Redesign and replace scales that have graduations which do not progress by 1, 2, 5, 10 or by those values multiplied by
- 10.
Provide SG Wide Range Level indicators and Condenser Vacuum indicators on right vertical board.
Provide a step stool for Chemical Addition Tank (CAT) indication.
SCHEDULE ST NP I
Provide step stool reading for various I
indicators above 70 inches on vertical board.
Relocate High Range Radiation Monitor trend NP recorders lower on panel.
If feasible, add two recorders.
Change scale plates to white on Pressur-ST izer Safety Valve Position Indication.
Replace scales that have more than nine ST graduations between numerals with ones showing numerals every 10th increment.
Replace existing trend recorders with ST recorders that can be read on real time basis.
45-TLG~2147B/rev. k-12 ASSOCIATED HEDS 22A02025 22A02058 22A02083 22A02084 22A02087 22A02220 22A02222 22A02409 20A02003 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED
- -1 I
Various indications identified e are only required for trending data collection. Alarms are provided to alert Operators of potential problems.
CAT level narrow range indication also is to be pro-vided at a lower position per CA41E.
CORRECTIVE ACTION #
CA73E CA74E CA75E CA76N CA77T CA78E CA79N CASON CA81E PROPOSED CORRECTIVE ACTION Adjust alarms to unmistakably alert/get Operators' attention.
lODBA above average ambient background generally adequate.
Coordinate with CAlE.
Rearrange switches so Accumulator Fill Valves are above Accumulator Drain Valves.
Improve labeling. Coordinate with CA60E.
Modify EOG Speed and Voltage control switch positions and labeling so raise is to right, lower is to left. Also include Main GEN VOLT REG Control Switches.
Coordinate with CA15E and CA23E.
Review procedures for use of shared equip-ment to ensure their adequacy.
Provide simulator training for Operators in doubling theory, I/M plotting closeness to criticality vs. rod insertion limits.
Provide narrow-range control, indication and annunciation for RWST temperature.
I No Ensure cooldown rates available on SPDS I
computer as backup to Process Computer.
Heatup/cooldown rate curves via graphics program.
Improve operability of Main Steam PORVS I
and provide status on Shift Turnover Sheet.
Provide remote throttle capability (trip NP close) to Bypass Valves for Main Steam Trip Valves on Benchboard in vicinity of Trip Valves.
45-TLG-2147B/rev. k-13 ASSOCIATED HEDS 20A02902 22A02905 22A03034 22A03601 22A04002 22A05002 22A05006 20A02212 22A02031 23002406 21A02412 23A02413 23003046 23003047 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED Root cause exists with capability of RWST chillers to maintain temperature at desired level.
e
CORRECTIVE ACTION #
CA82N CA83E PROPOSED CORRECTIVE ACTION SCHEDULE Upgrade Simulator Controls and Instrumen-ST/NP tation to reflect current control room.
Prior to installation in the CR, modifi-cations will be evaluated to determine the necessity and feasibility of installation in the simulator first.
Perform tactile change to inverse acting controllers and label appropriately to indicate 100% demand is full close.
ST 45-TLG-?.147B/rev. k-14 ASSOCIATED HEDS 23A01002 23001105 23A03102 20A03049 23A03218 JUSTIFICATION FOR PARTIAL OR NON-CORRECTION OF HED I
,I I*