ML20033D127
| ML20033D127 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/03/1981 |
| From: | Geier J ILLINOIS POWER CO. |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| U-0381, U-381, NUDOCS 8112070264 | |
| Download: ML20033D127 (7) | |
Text
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/LLINDIS POWER COMPANY L30-81 (l2-03)-6
/P 500 SOUTH 27TH STREET, DECATUR, ILLINots 62525 December 3,1981 Mr. James R. Miller, Chief g '<.
Standardization & Special Projects Branch phe l)
Division of Licensing G
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Dear Mr. Miller:
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Clinton Power Station Unit 1 y
Docket No.
50-461 Attached are details related to the following items which were discussed with D. Terao, Mechanical Engineering Branch, during a meeting on December 1,1981 to resolve issues for the Clinton SER:
ISSUES Feedwater Check Valves Number of Earthquake Cycles Used for Fatigue Reactor Internals Vibration Data for Prototype Preservice Exam and Preop Testing of Snubbers Pressure Isolation Valves The above items are considered by the NRC and IP to be confirma-tory for licensing purposes.
Sincerely,
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J.D. Geier y
Manager, Nuclear Station Engineering Attachments cc:
J.H. Williams, NRC Clinton Project Manager 3
H.H. Livermore, NRC Resident Inspector S j D. Terao, Mechanical Engineering Branch-j//
8112070264 811203 PDR ADOCK 05000461
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Issue Feedwater Check Valves IPC must provide the basis for assuming that the feedwater check valves can function adequately following a feedwater line rupture outside containment.
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Response
The additional loads imposed on the feedwater check. valves due to raoid closure as a result of a feedwater line break outside of
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to show that the stresses on the fe;An analysis is being performed containment have been considered.
edwater check valves disc and' seat area resulting from'this event will be within satisfactory limits.
This same analysis has been performed on larger valves of the same manufacturer and model type.
The results of that analysis show that the resultant stresses were.within acceptable limits.
-Since Clinton's valves are smaller and geometrically similar, _the re-sulting stresses'should be lower for the Clinton valves than those of the analyzed valves and should therefore be acceptable..IPC will provide confirmation of this when the Clinton specific analysis is completed.
It is anticipated'that this analysis will'be completed
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by the end of February, 1982.
I Action ~Requir_pd IP to provide the analytical results1by March 15, 1982.
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November 24, 1981 Dave Terao (MEB) Additional Question Question Related to Open Item #82_
1.
Describe the Feedwater Check Valves.
2.
Are the valves testable?
3.
Will the valves be tested or inspected periodically?
4.
We require the results of the analysis.
Response
1.
The inboard valves (lB21-F010 A, B are Anchor-Darling 18-inch, non-slam, tilting disc valves.
The outboard valves (lB21-F032 A, B) are Anchor-Darling 20-inch, non-slam tilting _ disc _ testable check valves.
They have air operators that permit exercising the valve part way shut with flow through the valve to verify that the disc is not stuck in position, and provide additional force to insure that the valves seal tightly when shut.
2.
The outboard valves are testable as described above.
3.
1B21 F032 will be exercised full stroke every 18 months (maximum) in accordance with 1WB-3412.
1B 21-F010 will be leak rate tested every 18 months in accordance with lWB-3420.
4.
The results of the analysis will be available in-February, 1982.
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i-Issue l
Number of earthquake cycles to be used for fatigue analyses.
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Response
l This was discussed at S&L/IP/NRE(MEB) meetings in March and April, 1981.
Additional substantiation is required.
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- Action Required-
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' IP to supply' additional.subst'antiatingLinformdtion.-
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f Issue Reactor-internals vibrati,n data for pro,totype.
(FSAR 3.9.2.3 discusses stresses on reactor internals caused by i
steady state vibration.
These stresses are limited to + 10,000
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psi based on predictions from operating reactors.
Additional assurance for BWR/6's is required by measurements at a prototype BWR/6.)
Response
The use of Kuosheng data as justification for EUR/6 design was accepted by MEB at~ S&L/IPC/NRC meetings in April,1981.
p However, the Kuosheng data is not yet available.
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-IP supplygKuosheng' data;to;MRC.-
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Issue Preservice Exam and Preop Testing of Snubbers (Because of numerous operational problems with snubbers, NRC requires an extensive pre-service examination of them.)
Response
'During the S&L/IPC/NRC(MEB) meetings in March and April, 1981, IPC committed to address all of NRC's concerns in our Pre-service testing program.
This program is scheduled to be completed and-submitted March.1982~.
. ction' Required-
- Submit program.uhen'conplete.-(March 1982)-
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Issue Pressure Isolation Valves (For isolation valves between low pressure and high pressure (reactor) systems, NRC has developed leak rate, testing, limiting conditions for operation, and monitoring requirements.)
Response
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.In the MEB meetings (S&L/IPC/NRC) in March and April, 1981, we
-committed to basically.LaSalle's answer.
Our answer,'Q&R MEB(DSER) item 87,' included lists of:-valves involved and specific protection measures.
Based on telecon between P. E. Walberg (IPC) and Dave Tarao (NRC-MEB) on'11/19/81 NRC is still evaluating our response.
They need no additional information from IPC.
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