ML19225D009
| ML19225D009 | |
| Person / Time | |
|---|---|
| Issue date: | 07/18/1979 |
| From: | Olshinski J NRC - TMI-2 LESSONS LEARNED TASK FORCE |
| To: | NRC - TMI-2 LESSONS LEARNED TASK FORCE |
| References | |
| NUDOCS 7908030493 | |
| Download: ML19225D009 (4) | |
Text
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UNITED STATES NUCLEAR R EGULATORY CO.'.1MisalON y;m g
WASHINGTON, D. C. 20555
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JUL 1 S 1378 MEFSRANDUM FOR: Lessons Learned Task Force FROM:
John A. Olshinski, Lessons Learned Task Force
SUBJECT:
AIF SYSTEMS AND EQUIPMENT DESIGN CRITERIA SUBCOMMITTEE MEETING On July 13, 1979, I met with the AIF Systems and Equip: rent Design Criteria Subcommittee. Enclosure 1 lists the subcommittee membership.
The subccm-mittee met on 12 and 13 July 1979 to discuss the various topics listed in.
Subcommittee member responsibilities for each topic are also listed in Enclosure 2.
I discussed various Lessons Learned work or recomendations that impacted these topics.
In addition, I indicated the propos'd schedule of publishing NUREG-0578 (TMI-2 Lessoas Learned Task Force Statue Report and Short Term Recommendations).
Particular suggestions or recorraendations that uei made by the subcommittee included:
1.
Considerations of possible negative impac.s of containment inerting be< ause of restricted access to equipment and possible negative health effects on plant personnel.
2.- Evaluation of the use of stainless steal cladding as a preventative measure in limiting combustible gas generation vice the use of inert-ing of containments as a mitigation measure.
3.
Consideration of evaluation of balance-c 1 2iant items because of their impact on the initiation and mitigaticn of avents as well as their impact on operator actions necessitated because of balancc-of-plant initiated events.
4.
Consideration of discussicns with Naval teactors concerning their quality control and system classification requirements " hen evalua-ting adequacy of current safety grade vi. non-safety grade classifi-cation of systems and components.
Additional discussion was held concerning analysis of core uncovery symp-tcms and the necessity for reactor vessel level detection instruentatioT1.
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, JUL 1 8 13/d The subcommittee presertly intends to make recomendations on their assigned areas by mid-October.
I encouraged the subcorrittee to maintain contact with the Lessons Learned Task Force.
I also encourage members of Lessor.s Learned to maintain contact with the subconnittee through Fred Stetson (AIF).
The subconnittee work in review of systems and design criteria can provide an expanded informational base to the Lessons Learned Task Force in the evaluation of these areas.
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[ Lessons Learned Task Force John A. Olshinski cc:
F. Stetson (AIF)
PDR e
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ENCLO5URE 1 SYSTEMS 6 EQUIPMENT DESIGN CRITERIA SUBCOMMITTEE CHAIRMAN:
Dr.
D.
Clark Gibbs SECRETARY:
Fred.
T.
Stetson, Jr.
Director of Nuclear Activities Mgr. Reactor Licensini Middle South Services, I n_c.
and Safety Box 61000 Atomic Industrial Fo rt New Oricans, Louisana 70161 7101 Wisconsin Avenue 504/329-5262 x.
271, 217 Washington, D.
C.
200:
Telecopy:
x.
262 301/654-9260 x.
268 Vice ' Chai rman :
Roy H.
Dunham Director of Engineering Design Tennessee Valley Authority W 11 A 9, 400 Commerce Avenue Knoxville, Tennessee 37902 615/632-2651 Robert Spilker Assistant. Manager Nuclear Safety Mr. John MacAdoo Project Engineer Ebasco Services, Inc.
Westinghouse Ele.tric Company 19 Rector Street P.
O.
Box 355 New York, New York 10006 Pittsburgh, Pa. 15230 212/785-S087
- 12/373-4374 Dr. Donald H.
Roy Manager Engineering Oc.M.4 T W // sa Nuclear Power Generation Div.
Gibbs 6 Hill, INc.
Babcock 6 Wilcox 393 Seventh Avenue P.
O.
Box 1260 New York, New York 10001 Lynchburg, Virginia 24505 212/760-4000 8 74 / 3 8 4 - 5111 x. 2375 James Ds. C raw fo rd Mr. Carroll Bitting Director, Plant Engineering Manager of Proj ects Power Systems Division Gilbert Commonwealth Associates Combustion Engineering,.Inc.
525 Lancaster Avenue 1000 Prospect Hill Road Reading, Pa. 19603 Windsor, Connecticut 06C95 215/775-2600 x.
2645 2 0 3/ 6 3 8 - 1911 x. 3 313 Mr. Ken Swarts
$.rapua J. /M " i , /
Senior Engineering Mant er American Electric Power Company Brown 5 Root, Inc.
P.
O.
Box 3 2 Broadway
Mike Kolar
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41f/855-2660 bl Mirn j [4M"I NRC
Contact:
John A.
01shi,nski, DSS '
Owners Groups Liaisons 440 004 B6W:
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ENCLOSURE 2 Containment Isolation (Frank Hutchinson)
Backfit diverse actuation required by SRP 6.2.4.
Rethink essential and non-essential systems.
Loss of component cooling water to RCP motor bearings.
Loss of component water to RCP seals.
Criteria for actuation.
Criteria for systems isolated.
Ability t" pump back gases and liquids to containment.
Emeroency ?ower Supplies (John MacAdoo)
Pressurizer Heaters (i.e. need to maintain hotleg subcooling with loss of offsite power or use of an alternate pressure source e.g. inert
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gas,iir compressor, or controllable head pump).
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PORV and block valves.
Pressurizer level indicatcr.
Reactor coolant pumps (e.g. pon) mot. ors or reduced voltage /frequenc. -
capability of pump to accommodate low speed operation).
Reliability of AC/DC power supplies - onsite and offsite.
Adequate Core Cooling (Don Roy)
Instrumentatior, and detection of inadequate core cooling.
RHR design basis and adequacy; access capability and equipment locations.
Increase letdown cooler capacity.
Prevention through design of degraded cooling.
core cooling systems containment systems radwaste and effluent systems Analysis of core uncovery symotoms.'-
Reactor vessel level detection.
Post Accident Hydrogen Control (Roy Dunham)
Provide reliable and dedicated penetraticns for purge and reccrbiner systems.
Inert all mark I and II containments.
(Vermont Yankee and Hatch).
Provide capability to use recombiners at all plants.
Filtered, vented containments on PWR's.
Instruments to Follow Accident (Ken Swarts)
Improve post-accident sampling.
Increase range of effluent monitors.
Provide bi-cange containment monitor.
Impre,e in-plant and effluent iodine measurement.
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Rsg. Cuide 1.97 Rev.1, August,1977 - implementation.
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_ 2-Safety and Process System Design Classifications (Bob Spilker)
Reliabil[ty.
Environmental qualification.
Power supply.
Establishment of a class 2E and 3E designation.
Miscellaneous (NSSS) (Ed Scherer)
Lcw tenperature overpressore protection.
Reactor coolant system venting.
Miscellaneous (BOP) (Steve Milioti)
Auxiliary building ventilation and filtration.
Radiation control for systems outside containment.
Perform leak test ar.d orovide tech specs for safety and process systems.
Perform shielding review for safety and process systems.
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