ML20213E336
| ML20213E336 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Salem |
| Issue date: | 03/04/1983 |
| From: | Silver H NRC - SALEM GENERIC IMPLICATIONS TASK FORCE |
| To: | Mattson R NRC - SALEM GENERIC IMPLICATIONS TASK FORCE |
| Shared Package | |
| ML20213E339 | List: |
| References | |
| FOIA-87-152 NUDOCS 8303100360 | |
| Download: ML20213E336 (3) | |
Text
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UNITED STATES
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if..C%. o March 4, 1983 MEMORANDUM FOR:
Roger J. Mattson, Chairman, Salem Generic Implications Task Force FROM:
Harley Silver, Task Force Project Manager
SUBJECT:
RRG MEETINGS ON SALEM EVENT RRG
.DATE TIME LOCATION B&W 3/8/83 9:00AM Phillips Bldg. P-ll8, Bethesda, Md.
CE 3/9/83 9:00AM Phillips Bldg. P-422, Bethesda, Md.
GE 3/10/83 9:00AM Bethesda GE Offices -
7910 Woodmont Avenue Suite 203 Bethesda, Md.
W 3/11/83 9:00AM MNBB, Room 1713, Bethesda, Md.
PURPOSE:
To discuss generic implications of the Salem event of February 25 (see attached agenda)
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PARTICIPANTS:
Salem Task Force Members (see attached list) + RRG Members Harley i ver, Project Manager Salem G eric Implications Task Force i
Attachments :
As stated e
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SALEM GENERIC IMPLICATIONS
_ AGENDA FOR'RRG MEETINGS, MARCH 8-11, 1983' 1.
Review design philosophy for reactor protection system with emphasis on reTiability of trip breakers and associated hardware / electronics.
2.
What scram system designs exist in operating plants and plants under construction? Provide design detail down to component 1.evel with emphasis on relays.
3.
Interface with vendor - provide us with vendor SILs (overall RPS, safety-rel ated relays and breakers).
Describe philosophy, general m'ethods of control and QA for this interface.
4.
Review operating experience as follows:
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a.
35 scram breaker failures in PWR.since 1973.
b.
Failures of relays in other safety systems.
c.
Failure of preventive maintenance on safety-related equipment.
d.
Failure to classify components correctly.
e.
Describe atten, tion paid to recurrent failures.
5.
Identify your use of equipment similar to undervoltage relay in Salem RPS.
a.
any relay in RPS c.
UV relays in any safety system l
d.
other "similar equipment" of concern to you 6.
Discuss general management approaches to the following:
Assurance of proper classification of safety-related components Operating event analysis before startup and in general Auditing of preventive maintenance and procurement to assure proper following of safety classification 7.
Are ATWS procedures in place today?
8.
Should there be manual reactor trip after each automatic trip?
9.
For loss of auto reactor trip on achieving 100% power on first startup after refueling, how long does operator have to prevent exceeding service level C, assuming loss of feedwater, if the turbine trip functions as presently designed? In SWRs, you may assume the recirculation pump trip functions as designed.
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SALEM GENERIC IMPLICATIONS TASK FORCE Manacement Oversicht R. Mattson, NRR
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J. Heltemes, AEOD
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Jordan, IE J. 01shinski, Reg. II M. Ernst, RES R. Starostecki, Reg. I Task Force R. Mattson, Chairman, NRR G. Holahan, Tech. Director, NRR, ORAB H. Silver, Task Force PM, NRR, DL E. Rossi, NRR, ICSB C. Graves, NRR, RSB W. Lanning, AEOD P. Shemanski, NRR, EQB W. Raymond, Reg. I W. Kennedy, NRR, PTRB Part-Time Members
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S. Israel, NRR, RRAB P. Baranowski, RES, DRA J. Partlow, IE, ORPB
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