ML17325A934
| ML17325A934 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/29/1988 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| AEP:NRC:1069, IEB-88-008, IEB-88-8, NUDOCS 8810070047 | |
| Download: ML17325A934 (7) | |
Text
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. A,CCEIZRATED
'UTION DEMONS TION SYSTEM REGULA i INFORMATION DISTRIBUTIO YSTEM (RIDE)
PiACJESSION NBR:88100'70047 DOC.DATE: 88/09/29 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana 05000315 50-316 Donald C.
Cook Nuclear Powe Plant, Unit 2, indiana a
05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION
'URLEYPT.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Provides response to NRC Bulletin 88-008 re thermal stresses in piping connected to RCS.
DISTRIBUTION CODE:
ZE16D COPIES RECEIVED:LTR /
ENCL
/
SIZE:
TITLE: Bulletin Response 88-08 Thermal Stress in Piping to RCS.
NOTES:
RECIPIENT ID CODE/NAME PD3-1 LA STANG,J INTER1NAL: AEOD/DOA AEOD/DSP/TPAB NRR HUM,M NRR RIVENBARK,G NRR/DEST/ADS 7E NRR/DOEA/EAB 11 NRR/DREP/EPB'0 NUDOCS-ABSTRACT RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD3-1 PD AEOD/DSP NRR HARTZMAN,M NRR REEVES,E.A.
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ILRB12 REG FIL 02 FILE 01 NRC PDR COPIES LTTR ENCL 1
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1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 24 ENCL 23
Indiana I'itichigan Power Company P.O. Box 16631 Columbus, OH 43216 pteszrm NECHICA&f POMfÃlR AEP:NRC:1069 Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
RESPONSE
TO NRC BULLETIN NO. 88-08:
THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS U.S. Nuclear Regulatory Conunission Attn: Docrunent Control Desk Washington, D.C.
20555 Attn: T.
E. Hurley September 29, l988
Dear Dr. Hurley:
The purpose of this letter is to provide our response to the first of two reporting, requirements stated in.NRC Bulletin 88-08, "Thermal Stresses in Piping Connected to Reactor Coolant Systems."
The bulletin and its two supplements address unisolable sections of piping connected to the reactor coolant system that can be subjected to stresses from temperature stratification or temperature oscillations that could be induced by leaking valves and that were not evaluated in the design analysis of the piping.
In accordance with Action Item 1 of the bulletin, we have reviewed systems with unisolable sections of piping connected to the reactor coolant system and identified those lines that may have been subjected to excessive thermal stresses.
The results of our review are provided in the attachment to this letter.
The attachment also includes a schedule for completing Action Items 2 and 3 of the bulletin.
Action Item 2 requires non-destructive examination of the piping sections identified by our review in order to provide assurance that there are no existing flaws.
In accordance with the
- bulletin, we propose to complete this non-destructive testing on Unit 2 piping dirring this current steam generator replacement/
refueling outage and the Unit 1 piping during the 1989 refueling outage.
Action Item 3 requires planning and implementing a program to ensure that applicable piping will not be subjected to sufficient Y~pk
Dr. T.
E. Murley AEP:NRC:1069 stresses that could cause fatigue failure.
This action will also be complete'd as indicated above; Unit 2 during 'this current outage and Unit 1 during the 1989 refueling outage.
A letter of completion will be submitted for the Donald C.
Cook Nuclear Plant Units 1 and 2, per the completion schedules contained in Action 4 of the bulletin, after the Unit 1 1989 refueling outage.
Sincerely, M
. Alexich Vice President ldp Attachment cc:
D.
H. Williams, Jr.
W.
G. Smith, Jr.
- Bridgrqan R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis
- Region III
COUNTY OF FRANKLIN Milton P. Alexich, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power
- Company, that he has read the foregoing response to NRC Bulletin No. 88-08, "Thermal Stresses In Piping Connected To Reactor Coolant Systems" and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
Subscribed and sworn to before me this day oZ
//
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hOMRY PU""LIC, SlhlE OF OIIIO ilYOOMMISSIOII EXPIRES MhKH I2. 199l
ATTACHMENT TO AEP:NRC:1069 ACTION 1 COMPLETION CONFIRMATION, REVIEW RESULTS, AND SCHEDULES FOR COMPLETING ACTIONS 2 AND 3
Attachment to AEP:NRC:1069 Page 1
The following is Indiana Michigan Power Company's response to NRC Bulletin No. 88-08 as applicable to the Donald. C.
Cook Nuclear Plant.
Action 1 Com letion Confirmation and Results of Review Ve confirm that a review of unisolable sections of piping connected to the reactor coolant system in accordance with Action 1 of NRC Bulletin No. 88-08 has been completed.
The following piping sections were identified as having the potential for being subjected to high-cycle thermal stress caused by leaking valves:
o One 3" alternate charging line to loop 1 cold leg o
One 2" auxiliary pressurizer spray line o
Four 1 1/2" high-pressure emergency core cooling system injection lines (one injection line to each cold leg)
The potential for the subject occurrence is present when an interacting system is capable of overcoming reactor coolant system pressure (2250 psi) during power operation.
The only such systems at the Cook Nuclear Plant are the chemical'nd volume control system and the high-pressure portion of the emergency core cooling system.
Both of 'these systems are designed to flow into the reactor coolant system during either normal or
. emergency conditions.
The motive forces used by both systems are provided by the charging pumps, which have an operating discharge pressure of about 2500 psig.
Other systems that inject into the reactor coolant
- system, i,.e.,
the safety injection system and the residual heat removal system (maximum design discharge pressure of 1725 psig and 205 psig, respectively),
are not operated during normal power operation.
Additional chemical arid volume control system lines that inject into the reactor coolant system were also reviewed.
These lines are the reactor coolant pump seal injection lines and the normal charging line.
In both cases, flow is continuous during power operation and, therefore, these piping sections are not subjected to this thermal fatigue mechanism.
2)
Schedule for Com letin Actions 2 and 3
In accordance with Action 2, non-destructive examinations will be performed on the unisolable sections of piping previously identified as having the potential for being subjected to high-cycle thermal
Attachment to AEP:NRC:1069 Page 2
stresses.
Ultrasonic and radiography testing techniques are being evaluated to provide the best method or combination of methods to provide assurance that there are no existing flaws.
Non-destructive examinations will be performed on the identified Unit 2 piping sections during the present outage.
Unit 1 examinations will be performed during the next refueling outage, which is scheduled in the first quarter of 1989.
A preliminary analysis indicates that the piping sections identified by our review are less susceptible to thermal fatigue than those discussed in the bulletin and its supplements due to piping geometry differences.
However, in accordance with Action 3, a long-term assurance program is being developed and will be implemented in Unit 2 by the end of the present
- outage, and in Unit 1 during the next refueling outage in 1989.