ML20080B051
| ML20080B051 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/01/1984 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-TM 5211-84-2023, GL-82-33, NUDOCS 8402060440 | |
| Download: ML20080B051 (8) | |
Text
GPU Nuclear Corporation U Nuclear
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Middletown, Pennsylvania 17057 717 944-7621 TELEX 84-2386 Writer"s Direct Dial Number:
February 1, 1984 5211-84-2023 Office of Nuclear Reactor Regulation ATTN:
D. G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Eisenhut:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Safety Parameter Display System NUREG-0737 (Item I.D.2)
This letter provides information about the TMI-1 SPDS based on our August 4, 1983 (updated November 28, 1983) submittal to the Commission entitled " Licensee Comments on Commissioner Gilinsky's Tentative Conclusion" Appendix A.
In the document we stated our intentions to provide the MlC with
... identification of any additional instruments and schedule for implementation..." provides the current list
- of instrumentation we have identified for an operational ' basic' and ' upgraded' SPDS. Our ' basic' SPDS will satisfy the major requirements for four o# the five identified critical safety functions.
The ' basic' SPDS will include parameters presently in the plant process computer data base. Upgrades to the basic SPDS will incorporate parameters from existing and new instrumentation not currently in the process computer data base.
At this time, our target to connlete upgrades to the ' basic' SPDS is the first available outage of sufficient duration following June 1985.
- However, we have initiated planning and scheduling in an atteript to integrate this new instrumentation at the same time we declare the ' basic' SPDS operational.
This accelerated goal is a function of procurement lead time and plant availability.
- Althcugh we consider the list complete at this time, as further analysis and detailed development of the SPDS continues, we will update the list and notify your staff as appropriate.
BOY 8402060440 840201 tion is a subsidiary of the General Public Utihties Corporation 0
PDR ADOCK 05000289 V
PDR E l
. describes our schedule for implementation to fulfill the various commitments made in our response to Generic Letter 82-33 and updates the information supplied in our April 15, 1983 letter by incorporating changes to the description of the system.
Finally, we wish to clarify our intentions for the SPDS as stated by the i
Staff's memorandum of the December 16, 1983 meeting. Our intent is to have operational ' basic' SPDS by the end of 1984. We will attempt to upgrade this
' basic' SPDS with the new instrumentation at the same time. But, as expressed above, our target to complete upgrades will be during the first appropriate outage after June 1985.
We trust this information and attachments will clarify and apprise the Staff of our progress in the implementation of the TMI-l SPDS.
Sincerely, f
W
/
H. D. Hukill Vice President - TMI-l cc:
J. Van Vliet R. Conte i
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ATTACINENT 1 SAFETY PARAMET8 DISPLAY SYSTEM Critical Safety Functions PARAMETERS 1
2 3
4 5
REACTOR TRIP SIGNAL 3 X X
EFFECTIVE FULL POWER DAYS (EFPD) 3 X POWER RANGE POWER 3
X POWER RANGE IH3ALANCE 3
X SOURCE RANGE START UP RATE 3 X INTERMEDIATE RANGE START UP RATE 3 X RCS WIDE RANGE PRESSURE 3
X STEAM GENERATOR PRESSURE 3
X REACTOR BUILDING PRESSURE 3
X C0tOENS8 VACUUM 3
X RCS WIDE RANGE COLD LEG TEMPERATURE 3
X RCS WIDE RANGE HOT LEG TEMPERATURE 3
X INCORE THERMOCOUPLE TEMPERATURE 3
X X
REACTOR BUILDING TEMPERATURE 1
X X
HEATUP/COOLDOWN RATE 3
X X
ifACTOR BUILDING SLNP LEVEL 3
X REACTOR BUILDING FLOOD LEVEL 3
X REACTOR VESSEL WAT8 LEVEL 2
X X
HOT LEG WATER LEVEL 2
X PRESSURIZER LEVEL 3
X i
RCS TOTAL FLOW 3
X RCS LETDOWN FLOW 3
X RCS MAKEUP FLOW 3
X HIGH PRESSURE INJECTION FLOW l
X MAIN FEEDWATER FLOW 3
X REACTOR COOLANT PLMP STATUS 3
X X
CIRCULATING WATER PLNP STATUS 3
X ROD ItOEX 3 X REACTOR BUILDING HYDROGEN MONITOR 3
X RM-L1 Lo (Letoown) 1 X
RM-L2 (A Loop Decay Heat Closed) 1 X
RM-L3 (B Loop Decay Heat Closed) 1 X
RM-L9 (Intermediate Closed) 1 X
RM-A2 GAS / PARTICULATE / IODINE (RB Atmosphere) 1 X
X RM-A4 GAS / PARTICULATE / IODINE (FHB Atmosphere) 1 X
RM-A5 (Condenser Exhaust) 1 X
RM-A6 GAS / PARTICULATE / IODINE (Aux Bldg Atm) 1 X
RM-A8 GAS / PARTICULATE / IODINE (Plant Stack) 1 X
l RM-A9 GAS / PARTICULATE / IODINE (RB Stack) 1 X
PM-G8 (Reactor Building Dome) 1 X
X HM-G26 (A Loop Steam Rellef) 1 X
RM-G27 (B Loop Steam Relief) 1 X
BORON CONCENTRATION (Grab Sample) 3 X i
. -. -.,,. ~. _.. -.... _..,. -. _,,
l ATTACINENT 1 (Cont'd) i t
CRITICAL SAFETY FUNCTIONS 1.
Reactivity Control 2.
Reactor Coolant System Inventory Control 3.
Primary Side Heat Removal 1-4.
Radiation Control 5.
Reactor Building Environment i
NOTES 1.
Parameters presently available in the control room but not available on the plant process computer.
2.
Parameters which are not presently installed at TMI-1.
i 3.
Parameters presently in the plant process computer data base.
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ATTACHMENT 2 TMI-l SCHEDULE FOR SPDS IMPLEMENTATION A.
THE TMI-l SPDS In our April 15, 1983 letter, we described our designs and status for the SPDS as a subset of the Plant Computc1 System. The following provides an update and elaboration of that description: The TMI-l SPDS will be available in a ' basic' form by January 1,1985. The ' final' form is scheduled to be completed by June 1985 or the first outage after this date, of sufficient length to allow the new instrumentation to be connected to the Plant Process Computer System. However, planning and scheduling have been initiated in an attempt to implement the ' final' form concurrent with the ' basic' SPDS.
The SPDS has evolved as a result of work done to define the objectives of the SPDS and the parameters required to meet these objectives.
' is a complete list of the SPDS critical safety functions and the parameters associated with each function. This list is expected to go through minor changes as the safety analysis, user guideline, and CRT display development work continues. Even after the SPDS has been implemente1, operational experience with the system may cause changes in the pare,aeter set.
B.
BASIC SPDS The ' basic' SPDS is that portion of the final SPDS which is a subset of the 2500 points currently available in the computer data base. These i
parameters are jdentified by Note 3 in Attachment 1.
The ' basic' SPDS l
will satisfy the major requirements of four of the five critical safety functions.
A subset of the ' basic' SPDS has already been implemented at TM1-1 in the form of a post trip pressure-temperature plot.
This plot is used to evaluate core cooling and heat removal from the reactor coolant j
system. This display suoports the use of symptom-oriented emergency procedures developed from the ATOG program. Operators and Shift Technical Advisors are taught how to interpret this display by a computer aided instruction course.
C.
FINAL SPDS The ' final' SPDS will include the ' basic' SPDS plus additional l
parameters which are available in the control room but not on the Plant Process Computer System. These additional parameters are identified by Note 1 in Attachment 1.
The ' final' SPDS will also include new parameters which are presently being installed at TMI-1.
These i
parameters are identified by Note 2 in Attachment 1.
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1 SCHEDULE The implementation schedule for the SPDS is shown on Figure 2-1 and the important milestones are discussed below.
o SPDS SAFETY ANALYSIS An SPDS safety analysis is currently being performed, and Critical Safety Functions (CSF) which would describe the safety status of the plant have been identified. Parameters for each CSF to satisfy the objectives for that CSF have also been identified and include additional instrumentation / parameters which require incorporation into the existing plant computer data base. The SPDS parameters will alert the user through warnings or alarms of abnormal conditions and will be tested (analytically) against a range of transients / accidents to determine if each event in a transient can be monitored and evaluated adequately. A safety analysis report will be submitted to the NRC by April 3D, 1984.
o USER GUIDELINES i
User guidelines will be developed to aid the user in evaluating and dealing with normal and abnormal conditions.
These guidelines will also serve as the basis for developing CSF displays and for training
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the SPDS users.
o IMPLEMENTATION PLAN In our April 15 and July 12, 1983 letters, we provided a major milestone schedule for implementation of the SPDS. Further refinement to this plan together with the verification / validation program will be submitted to the NRC by June 30, 1984.
o DISPLAYS DEVELOPED i
CRT displays will be developed to provide concise and unambiguous information to the user. Thase displays will be accessible by using the CRT presently available in the control room. The SPDS warnings and alarms will be incorporated into the existing alarm processor. The displays and alarms will have a human factors review performed on them prior to implementation.
o DISPLAYS IMPLEMENTED In this phase, computer programs will be written which allow the displays to be implemented in real time in the control room.
The programs will have a verification and validation process performed on them prior to implementation.
o USERS TRAINED The users will receive proper training on the SPDS philosophy, design and use.
This training will in part be developed from the user guidelines. This training will also include the observation of how the SPDS responds to a few transient / accident scenarios developed for this purpose.
PROCESS COWUTER UPGRADE t
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Independently of SPDS implementation, longer range plans for the process computer include replacement with a new computer system providing two fully i-1' compatible and redundant computer systems which will be powered from an uninterruptible power supply.
These improvments which are beyond the requirements of NUREG-0737, will enhance the SPOS in the areas of redundancy and reliability.
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FIGURE 2-1 i
l SPDS I WLEMENTATIDN SCHEDULE 1984 1985 i
(
)
i APRIL MAY JUNE JULY AUGUST SEPT OCT NOV DEC JANUARY l
Refinements l
SPDS User to Imple-Displays Displays Users Basic i
Safety Gi.ide-mentation Developed
.'mple-trained SPDS i
Analysis lines plan to mented available WC i
1 Description of verification JUNE 1985 and validation plan Final SPDS Available*
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4 o May be delayed until the first outage of sufficient length to allow new instrumentation to be connected to the Plant Process Computer System.
However, planning and scheduling have been initiated to attempt to have implemented upgrades to Basic SPDS by January 1985 if the plant is available for installation for new signals.
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