ML17194B231
| ML17194B231 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/27/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Delgeorge L COMMONWEALTH EDISON CO. |
| References | |
| TASK-2.D.1, TASK-TM NUDOCS 8208050057 | |
| Download: ML17194B231 (5) | |
Text
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NRC PDR Docket Nos. 50-237
.:., '" ", 50-249 local PDR P. O'Connor f
Mr. L. Del George Director of Nuclear Licensing Commonwealth Edison Company P. o. Box 767 Chicago. Illinois 60690
Dear Mr. DelGeorge:
.. ORB #2 Rdg D Eisenhut OELD OI&E ( l)
. JHegner SNorris NSIC ACRS Cl 0 )_
JHeltemes D. Vassallo
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - TMI ITEM II.D.1.
PERFORMANCE TESTING OF BWR ANO PWR SAFETY /RELIEF VALVES Re:
Dresden Station. Units 2 and 3 D. Crutchfi.el-d Z. Rosztoczy R. Wri_ght Gray File The final generic report (NEDE-24988-P. Analysis of Generic BWR Safety/
Relief Valve Operability Test Results) on TMI Item II.D.1 was submitted to us for review by the BWR Owners Group by letter dated September 25, 1981. This final report contained the. generic test results intended to demonstrate the operational adequacy of BWR safety/relief valves (S/RV).
You were a participant in the generic test program and have endorsed the results.
/
In order to complete this item, the applicability of the generic test results must then be demonstrated for the specific S/RVs employed at Dresden Station, Units 2 and 3*.
By letters dated July 1 an~ October 1, 1981, you previously submitted infonnation to address that issue.
We have reviewed those submittals and f1nd that they do not provide adequate bases for your conclusion that the test results presented in NEDE-24988-P are applicable to Dresden Station, Units 2 and 3. Therefore, additional information is necessary befor~ we can complete our review of this item.
The enclosed Request for Additional Information (RAI) identifies those areas for which additional information is necessary to adequately d~mo11.-
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ADOCK 05000237 PDR OFFICE.......,.................
SURNAME.........................
DATE.........................
NRC FORM 318 (10-80) NRCM 0240...
OFFICIAL RECORD COPY USGPO: 1981-:-335-960
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Mr. L. De 1 George
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strate the applicability of the generic report to Dresden Station. Units 2 and 3.
We request that you respond to the RAI within 45 days of receipt of this letter. This request for infQnnatiOn is applicable only to Dresden Station. Units 2 and 3; therefqre, OMB clearance is not required under P.L. 96-.511.
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Enclosure:
Request for Additional lnfonnat1on cc w/encl:
See next page
. Sincerely, origlna1 *signed lil Domenic B. Vassallo. Chief Operating Reactors Branch #2 Division of Licensing DL:ORB#2 OFFICE. *****sHofriP'"
SURNAME~ ************************
- DL :ORB#2 (ORB #5
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JHegner :ms
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7 /~/82 DATE. ************************ :::::~!.~?.~~:::::: ::::~?:~~?.:~:~::::::: ::~?.1.~~1.:~:?::::::: ::::?.. /iii.a?.:::::: ::::::::::::::::::::::::
NRG FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960..,.. '
Mr. L. DelGeorqe cc:
Robert G. Fitzgibbons Jr.
/
I Isham, Lincoln & Beale
.1
- Three First National Plaza Suite 5200 Chicago, IL 60602 Plant Superintendent i
Dresden Nuclear Power Station
~ural Route #1 Morris, Illinois 60450 Morris Public Library 604 Liberty Street Morris; Illinois 60451 U. S. Nuclear Regulatory Commission Resident Inspector's Office Dresden Station RR #l Morri~, Illinois 60450 Mary Jo Murray, Esq.
Assistant Attorney General Environmental Control Division 188 W. Randolph Street
.Suite 2315 Chicago, Illinois 60601 John F.* Wolf, Esq.
3409 Shepherd Street Chevy Chase, Maryland 20015 Dr. Linda W.
Littl~
500 Hermitage Drive Raleigh, North Carolina 27612 The Honorable Tom Corcoran
- U.S. House of Representatives Washington, D.C.
20515 Dr. Forrest J. *Remick 305 East Hamilton Avenue *-
State College, Pennsylvania 16801.
James G. Keppler Regional Administrator, Region III U.S. Nuclear Regulatory Commission 79~ Roosevelt Road Glen Ellyn, IL 60137
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Enclosure Requrr.J~~~~~~-l~n_formati on 1~~---~-l TMl Action.Ala~:II.D.l e*
Your October 1, 1981 letter does not provide the basis for your conclusion that the test results presented in NEDE-24988-P on safety/relief valve testing are applicable to Dresden Station Units 2 and 3.
Describe the 5asis thoroughly, as indicated below.
- 1.
The test program utilized a "rams head" discharge pipe configuration.
Dresden utilizes a "tee" quencher con-figuration at the end of the discharge line.
Describe the discharge pipe configuration used at Dresden and compare the anticipated loads on valve internals in the plant configuration to the measured loads in the test program.
Discuss the impact of any differences in 1 oads on valve operaoility.
- 2.
The test configuration utilized no spring ha~gers as pipe supports.
Plant specific configurations do use spring hangers in conjunction with snubber and rigid supports.
Describe the safety relief valve pipe supports used at Dresden and compare the anticipated loads on valve i"nternals for the plant pipe supports to the measured loads in the test program. _Describe the impact of any differences in loads on va 1 ve operability.
- 3.
Report NEDE-24988-P did not identify any valve functional deficiencies or anomalies encountered during the test program.
Describe the impact of valve safety function of any valve functional deficiencies or anomalies encountered during the program.
- 4.
Tfi.e purpose of the test program. was to determine valve performance under conditions anticipated to be encountered in the plants.
Describe the.events and antcip~ted conditions at Dresden for which the valves are required to operate and compare these plant conditions to the conditions in the test program.
Describe the plant features assumed in the event evaluations used to scope the test program and compare them to*plant features at Dresden.
For example, describe high level trips to prevent water from entering the steam lines under high pressure operating conditions as assumed in the test event and compare them to trips used at Dresden.
~ -- 5.
The valves are likely to be extensively cycled in a controlled depressurization mode in a plant specific application.
Was.this mode simulated in the test program? What is the effect of this valve cycling on valve performance and probability of the valve to fail open or to fail close?
- 6.
o:scribe how the values of valve Cv's in report NEDE-2498~-P wtll be used at Dresden.
Show that the methodology used ln the test program to determine the valve Cy will be consistent iwth the application at Dresden.
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