ML17326A421
| ML17326A421 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/19/1979 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 AEC:NRC:00253B, AEC:NRC:253B, NUDOCS 7912270284 | |
| Download: ML17326A421 (11) | |
Text
&WOOOOOOWHMOW REGULATO INFORNATlON DISTRIBUT10N STKN (RIDS)
ACCESS'ION NBR e 7912270280 DOC ~ DATE: 79/12/19 NOTARIZED ~
NO DOCKE'T. 0 FACIE:50"316 Donald C ~. Cook Nuclear Powei Plantr'On)t 2r Indiana 8
05000316 A&'fH;NAME.
AUTHOA AFF'ILIATIQN":
HUNTKRrR ~ ST Indiana 8 Hichigan Electric Co,'EC IP ~ TAHE
'EC'IP IENT AFFILIATI ON DEATUNrH.R.
. Office of NucT'ear Reactor Regulation V
SUBJECT:
Submits addi infoi re curl ent status of four requirements of NUREG-0578 concerning direct i,ndication of~ safety valve posit,ionrsubcooling meters"sys'ntegrity for. high radioactivity L post accidenti sampling.
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INDIANA L MICHIGAN ELECTRIC COMPANY P. O.
BOX 18 BO WLING GR E EN ST ATION NEW YORK, N. Y. 10004 December 19; 1979 AEP:NRC:00253B
'Donald C.
Cook Nuclear Plant Unit'No.
2 Docket No. 50-316 License No.
DPR-74 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Denton:
During telephone discussions with members of your staff on December
-18 and 19 we were requested to supply additional information concerning the most current status of four requirements in NUREG-0578.
These requirements are those for which we had previously indicated that we could not meet the NRC implementation date.
The four items are:
2.1.3.a Direct Indication of Safety Valve Position,,
2-. 1.3.b Subcooling Meter, 2. 1.6..a System Integrity for High Radioactivity, and 2.1.8.a Post Accident Sampling.
The NRC-required implementation date;, for these items established in NUREG-0578 is January 1, 1980.
Our previous two letters responding to NUREG-0578 are dated October 24 (AEP:NRC:00253) and November 26 (AEP:NRC:00253A).
On Item 2. 1.3.a,.Direct Indication of Safety Valve Position, we have taken all steps necessary, to insure that an acoustic monitoring system will be installed on the three pressurizer safety valves and on the common discharge header from the power-operated reli'ef valves by January 1,
1980.
The system will meet clarification items 1, 2, 3, and 4 of Mr. Eisenhut's October 30 letter.
The system will, in the long.term, meet clarification item 5; a proposed schedule for implementation of the environme'ntal qualification program will be provided at a later date.
The acoustic monitoring system is in
'ddition to the limit switches and temperature indication and alarm in the common discharge pipe displayed in the Control Room for the PORV's, and the individual discharge temperature indications and alarms displayed in the Control Room for the safety valves.
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Mr. H. R. Denton December 19, 1979 AEP:NRC:002538 On Item 2. 1.3.b, Subcooling Meter, the delivery date for the sub-cooling meter has been advanced ten days to January 15.
We are investigating methods to install the meter sooner than our currently scheduled April 1, 1980 date.
A Unit outage is not required for this work.
As an added step in providing information on saturation margin to the operators, we have written a program to be incorporated in the PRODAC,250 computer system as a substitute, for the subcooling meter until the meter is installed.
The process inputs include:
1)
Eight incore thermocouples, two per;. quadrant.
Selection of incore thermocouples will be made internally so that any eight thermocouples can be used.
2)
Eight reactor coolant system wide range RTD's, both hot leg and cold leg.
3)
Two wide range reactor coolant loop system pressures.
By selecting the lowest wide range pressure, the margin to saturation is calculated based on:
1)
Highest RTD reading 2)
Highest thermocouple reading 3)
Average of'RTD readings except for the highest RTD reading and the lowest RTD. reading.
4)
Average of all T/C readings except for the highest T/C reading and the lowest T/C reading.
These. calculations will provide four separate answers which will be recorded by the trend typewriter every fifteen minutes.
An existing annunciator will be alarmed when the alarm setpoint is reached or when there is an unreliable input.
The PRODAC 250 alarm typewriter will also alarm with a message being printed out.
The alarm setpoint can be varied.
The computer calculation can be output to various devices, such as:
trend typewriter, alarm typewriter, digital display and/or an analog recorder. by individual selection.
Attachment 1 gives further information on the,PRODAC computer.
h l'
Mr. H.
R. Denton December 19, 1979 AEP:NRC:00253B The experience with the PRODAC computer has shown a reliability of approximately 95'A.
- In case of loss of offsite power, the PRODAC continues to operate off its. own inverter fed by the station battery.
This computer program is in addition to the curves of saturation temperature versus reactor coolant pressure for which the operators have a procedure and have been instructed to use.
On Item 2. 1.6.a, System Integrity for High Radioactivity, we have identified the systems or portions of systems for leak test surveillance to be completed by April 1, 1980.
These systems will be included in our plant preventive maintenance program.
By January 1,
1980 we will have inspected, measured the leakage, and repaired as necessary, the reactor coolant letdown path and charging flow path.
The results of our test on these systems will be available for NRC inspection at the Plant by January 1,
1980.
We will continue performing the inspection program such that by April 1 or sooner, the remaining systems will be completed.
All initial system results will be submitted to NRC for review by April 1
or sooner.
This program will be performed on these systems at least once per refueling cycle.
The results of annual tests will be available for NRC review at the Plant.
We are currently developing a method of inspecting the systems which contain gases and will complete these in the program outlined above.
In addition to this preventive maintenance
- program, we have in place at Cook Plant the additional leakage
'detection systems indicated in our two previous letters.
We do not foresee requiring special equipment that would prevent us from completing this work by April 1, 1980.
Test procedures of liquid systems do not require a Unit shutdown.
The gas systems are presently being evaluated for impact on plant status during test.
On Item 2. 1.8.a, Post Accident Sampling, we will complete by January 1,
1980 the installation of two interim sampling systems for taking post accident samples; one to take samples of reactor coolant and the other to take a sample of containment atmosphere.
Modifications will be made and procedures in place by the end of the year.
We discussed the design of these interim sampling systems with members of your staff in a telephone conversation of December 10.
Our longer term program, in which we are working with an outside contractor,.still has a date of April 1, 1980 for submitting to you the description of plant modifications and target date for implementing major plant modifications.
Mr. H.
R. Denton December 19, 1979 AEP:NRC:00253B These additional steps being undertaken reflect positive action towards strengthening our position previously described in our two letters AEP:NRC:00253 and 253A.
We recognize the need to incorporate the lessons learned from the TMI-2 accident as quickly as is reasonably possible.
We will continue to periodically monitor the progress on these four items as well as the remaining NUREG-0578 requirements to make sure that we complete the required analyses and modifications on schedule.
Our schedule for returning Unit No.
2 to power is:
Close the containment - December 23 Criticality - December 25 Parallel - December 28 We request your approval to proceed with our startup on this
- schedule, including your issuing to us the staff evaluation report on the battery conversion for the turbine driven auxiliary feedwater pump which is needed to enter Mode 3.
Very truly yours, R.
S.
unter Vice President RSH/emc Attachment cc:
R.
C. Callen G. Charnoff John E.
Dolan R.
W. Jurgensen D. V. Shaller Bridgman
ATTACHMENT l DON>>
D C.
COOK NUCLEAR PLANT INFORHATION REVUIREO ON THE PRODAC
~0is Ia Information Displayed (T-Tsat, Tsat,
- Press, etc.)
Display Type (Analog, Digital, CRT)
Continuous or on Demand Single or Redundant Display Location of Display Alarms (include setpoints)
Overall uncertainty ('F, PSI)
Range of Display gualifications (seismic, environmental, IEEE323)
T-Tsat
- Temps, Pressures Digital Automatic, 4 per hour and on demand Single but backup for out ut Control Room
- Yes, 30 F
Adjustable Calcul.ator Type (process
- computer, dedicated aigital or analog calc.)
If process computer is usea specify availability. (" of time)
Single or reaunaant calculators Selection Logic (hignest T., lowest press) gualifications (seismic, environmental, IEE=323)
Calculational Technique (Steam Tables, Functional Fit, ranges)
Process Computer Approx.
95%
Single Highest T and lower pressure Functional Fit agrees with Steam Tables to accuracy o
part in a 1000.
Inout Temperature (RTO' or T/C')
Temperature (n mber of sensors and locat ons)
Range of temperature sensors Both See Note 1
8 RTDs,, hot 5 cold legs T/Cs 2
er uad.
RTOs 0-700 F
T/C 0-2500oF
Ur~"ertainty" of temperature sensors
('F at l
)
qualifications (seismic, environmental, IEEE323)
Pressure (specify instrument used)
Pressure
{number of sensors and locations)
Range of Pressure sensors Uncertainty* of pressure sensors
{PSI at l
)
gualificati'ons (seismic, environmental, IEEE323)
Elide range RTDs
= 3.5 F
T/Cs
= (6 F
RTOs - See Note 2
T/C-Control Grade llide Ran e
RCS 2
RCS Loo s 1
& 2 0 -3000 si 30 si See Note 2
Backuo Caoabil it Availability of Temp 6 Press Availability of Steam Tables etc.
Training of operators Procedures
.Procedure
& Sat.
Curves Pasted to Control Room Panel Yes Yes
~Uncertain-ies
..ust address conditions of forcea flow and natural circulation NOTE 1 - Input to P-250 NOTE 2 - See I&HPCo. response to IE Bul'jetin 79-01 dated June 28, 1979 (AEP:NRC:00253) further supplemented by our October 15, 1979 submittal AEP:NRC:00277.
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