ML19224A297
| ML19224A297 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/04/1978 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7812130109 | |
| Download: ML19224A297 (21) | |
Text
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UNITE D STATES
- w NUCLEAR REGULATORY COMMtsSION WASHINGTON, D. C. 20555 u;i 1978
%,......p s
DOCKET N0.
50-320 APPLICANT:
Metropolitan Edison Company FACILITY:
Three Mile Island, Unit 2
SUBJECT:
SUMMARY
OF MEETING ON STEAM LINE BREAK FIX Representatives of Met Ed and GPU and Burns and Roe met with members of the staff on October 19, 1978 to discuss the proposed fix for the steam line break problem on TMI-2.
An attendance list is enclosed.
The licensee requested the meeting to provide an updated description of the conceptual design of the modifications proposed to resolve the steam line break problem in accordance with conditions of the TMI-2 operating license. The attached handout formed the basis for Met Ed's presentation and was discussed in some detail.
Infomation in addition to that contained in the handout includes the following.
~
Faedwater isolation valves are Borg Warner gate valves, hydro-pneu-matically operated with 3-5 second closing time, with the capability of being manually closed.
They will be qualified to IEEE-323. The actuator assemblies are identical to those used or proposed in Cherokee, Perkins, Comanche Peak, Bellefonte, WPPSS-2, McGuire, Catawba, Byron /
Braidwood, Marble Hill, Seabrook, and Beaver Valley 2.
It was noted that the valves require Type C testing, or adequate justification for exception to tnis requirement.
We also expressed concern about assurance of returning the valves to their normal reition after testing, and about protection of cables to the valves from jet effects and pipe whip.
With regard to required analyses, Met Ed agreed to specifically identify which of the submitted analyses are apolicable to the new configuration and to provide any necessary additional analysis.
We agreed to consider the presented infomation and to indicate our concu rence with the conceptual design.
f
/ &,
Harley,dflyer, Project Manager Light Water Reactors Branch ?
2.als Division of Project Management
Enclosures:
As stated 7 / (
O Metropolitan Ediscn
- mnary DEC 4 17$
ccs:
George F. Trowbridge, E sq.
Alan S. Rosenthal, Esq. Chairman Shaw, Pittman, F at
- Trowbridge Atomic Safety and Licens ng 1800 1 Strc s, N.
U. S. Nuclear Regulatory Ccamission Washington, C C.
20036 Washington, D. C.
20555 Mr. I. R. Finfrock Jersey Central Power and I.ight Ccapay D r.
W. Reed Jchnson, Member Madison Avenue at A mch Bowl Road Atomic Safety and Licensing Morristown, New Jersey 07960 Appeal Board U.S. Nuclear Regulatory Commission Mr. R. Conrad Washington, D. C.
20555 Pennsylvania Electric Comoany 1007 Broad Street Jerome E. Sharfman, Esquire, vemoer Johnt, town, Pennsyl vani a 15907 Atomic Safety and Licensing Appeal Board Chauncey R. Kepford, Esq.
U.S. Nuclear Regulatory :0mmissicn Chairman Washingt:n, 3. C.
20555 York Ccmmittee for a Safe Environment 433 Orlando Drive State College, Pennsylvania 16801 Mr. J. G. Herbein Mr. Richard W. Heward Vice President Project Manager P. O. Box 542 GPU Service Corporation Reading, PA 19603 250 Cherry Hill Naad Parsippany, New Jersey 07054 GPU Service Corporation ATTN:
Mr. E. G. Wall ace Licensing Manager 260 Cherry Hill Roat Parsippany, New Jersev 07054 Edward Luton, Esq., Chairman Atomic Safety and L icensing Board U. S Nuclear Regulatcry Commission Washington, D. C.
'9555 Mr. Gustave A. Linenberger Atomic Safety and L icensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Ernest O. Salo Professor. Fisheries 9esearch Institute, WH-10 College of Fisheries University of Washington Seattle, Washington 93195 2.a20
h DEC 4 1978 ENCLOSURE MEETING - STEAM LINE BREAK - TMI-2 A.
S.
Dam, Burns and Roe L.
C.
Lanese, GPU Service Corporation R.
A.
Lengel, Met Ed J. W.
Cajigas, Met Ed C.
R.
Montgomery, GPU Service Corporation J. J.
Watts, USNRC, RSB P.
C.
Hearn, USNRC, ASB H.
Eltawila, NRC/ CSB Frank Ashe, NRC
O YE5 DEC 4 THREE MILE ISLAND, UNIT 2 NRC LICENSE CONDITION -
" SUBMIT APPROPRIATE SESCRIPTIONS AND ANALYSES AND MODIFY 19E SECONDARY (MAIN STEAM AND FEEDWATER) SYSTEMS SO THAT ThE CONSEQUENCES OF A SPONTANE0US BREAK ANYWHERE IN A SECONDARY SYSTEM LINE WILL BE MITIGATED ONLY BY SAFETY GRADE EQUIPMENT, WITH NON-SAFETY GRADE EQUIPMENT PERMITTED TO SERVE AS A BACKUP FOR THE ASSUMED SINGLE FAILURE OF SAFETY GRADE EQUIPMENT.
FOR THOSE PORTIONS OF THE SECONDARY SYSTEMS WHERE A BREAK MIGHT BE CAUSED BY A SEISMIC EVENT, METROPOLITAN EDIScN CCMPANY SHALL MODIFY THE SYSTEMS SO THAT ACCIDENT CONSEQUENCES WILL BE MITI-GATED ONLY BY SEISiilC CATEGORY I CCMPONENTS AFTER ASSUMING SINGLE FAILURE IN ANY SEISMIC CATEGORY I COMPONENT."
MODIFICATIONS TO SE INSTALLED BY END OF FIRST REFUELING CUTAGE.
10/19/78 2.322
OUTLINE OF PRESENTATION INTRODUCTION AND PURPOSE MECHANICAL DESIGN ELECTRICAL DESIGN CONFORMANCE TO STAFF POSITION ACCIDENT ANALYSIS SCHEDULE
PURPOSE
'lEACH CONCURRENCE WITH STAFF ON:
r CONCEPTUAL DESIGN DESIGN CRITERIA CONFORMANCE TO LICENSE CONDITION e
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FEEDWATER ISOLATION SYSTEM MAJOR FEATURES SYSTEM DESIGN REQUIREMENTS PROVIDE SAFETY GRADE ISOLATION OF A STEAM GENERATOR FOR MAIN STEAM LINE BREAK OR FEEDWATER LINE 3REAK PROVIDE CCNTAINMENT ISOLATION CAFADILITY FOLLCWING A MAIN STEAM LINE BREAK OR FEEDWATER LINE BREAK INSIDE THE REACTOR BUILDING WHILE ASSURING SATISFACTION OF SAFET'. REQUIRE-ME!!TS, PROVIDE OPERATIONAL RELI ABILITY TO i
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PLANT OPERATION ALL COMPONENTS QUALIFIED FOR SEISMIC EVENTS AND APPROPRIATE ENVIR0f:MENTS i
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O FEEDWATER ISCLATION SYSTEM MAJOR FEATURES (CONTINUED)
SYSTEM DESIGN CONCEPTS IWO FAST CLOSING ISOLATION VALVES PER FEEDWATER LINE, ONE INSIDE AND THE OTHER QUTSIDE CONTAINMENT TWO REDUNDANT ACTUATIONS PER VALVE, EACH USING 2 OUT OF 3 LOGIC FOR RELIABILITY ALL COMPONENTS CAPABLE OF TEST OPERATION DURING NORMAL PLANT OPERATION WITHOUT CCMPROMISING SAFETY FUNCTIONS DURING STARTUP CONDITIONS, FEEDWATER FLOW WILL BE ADMINISTRATIVELY LIMITED TO THE STARTUP REG'JLATING VALVES 9
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[NDEPENDENT CHANNEL ACTUATION AND EXERCISING MEETS NRC REGULATORY GUIDE 1.48 INCLUDING OPERABILITY DURING AND AFTER SEISMIC EVENT MEETS IEEE REQUIREMENTS FOR CLASS 1E DEVICES VALVE DESIGN SOLID WEDGE GATE VALVE VALVE CLOSES ON ENERGIZATION OF ONE OR E0TH SOLENOIDS STORED HIGH PRESSURE N 2 IS UTILIZED FOR VALVE CLOSURE 2.330
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THIS IS THE ORIGINAL ELOWCOWN ANALYSIS USING FEEDWATER CONTROL VALVES WITH A TURBINE STOP VALVE FAILURE AS THE SOUNDING CASE FEEDWATER LINE BREAK SYSTEM ANALYSIS.
DUE TO REPLACEMENT OF THE FEEDWATER CHECK VALVES, THIS ANALYSIS IS BEING REDONE.
FEEDWATER LINE BREAK PIPING ANALYSIS.
IHERM0 HYDRAULIC AND STRUCTURAL ANALYSES ARE BEING PERFORMED TO ASSURE THAT THE ISOLATION VALVES OPERATE AND SERVE THEIR DE-SIGN FUNCTION.
PIPE WHIP AND JET IMPINGEMENT ANALYSES ARE BEING PERFORMED TO ASSURE THAT LOADINGS DUE TO PIPE WHIP AND JET IMPINGEMENT DO NOT IMPAIR ISOLATION VALVE OPERATION.
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6-9 TMI-2 FEEDWATER ISOLATION SYSTEM ELECTRICAL DESIGN MAJOR FEATURES CLASS lE SYSTEM (IEEE 308-1974)
PROTECTI'/E SYSTEM (IEEE 279-1971)
CONFORMANCE TO SINGLE FAILURE CRITERION (IEEE-379-1972)
IHREE SEN31NG CHANNELS TO DEVELOP ACCIDENT SIGNALS IWO-0UT-OF-THREE LOGIC SENSING CHANNEL RELAYS CE-ENERGIZE TO ACTUATE IWO ACTUATION CHANNELS PER VALVE SOLEN 0 IDS ENERGIZE TO CLOSE VALVE CAPA3ILITY FOR CHANNEL TEST AUTOMATIC REMOVAL OF OPERATING SYPASSES INDICATION OF BYPASSES IN CONTROL ROCM COMPLETION OF PROTECTIVE ACTION MANUAL INITIATION IN CONTROL ROOM REMOVAL OF ONE CHANNEL FROM OPERATION WILL NOT INITI ATE PROTECTIVE ACTION 2.333
TMI-2 FEEDWATER ISOLATION SYSTEM ELECTRICAL DESIGN MAJOR FEATURES (CONTINUED)
SEPARATION AND INDEPENUENCE (IEEE 384-1974)
ISOLATION RELAYS FOR SENSING CHANNEL TO ACTUATION CHANNEL SEPARATION ALARMS NOT CONSIDERED WITHIN SCOPE OF SEPARATION CRITERIA WUALIFICATION TO APPLICABLE ENVIRONMENTAL REQUIREMENTS (IEEE 323-1971/
1974 WHERE EUUIPMENT IS AVAILABLE)
WUALIFICATION TO APPLICABLE SEISMIC REQUIREMENTS (IEEE 344-1975) 2.334
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2.336
CONFORMANCE TO STAFF POSITION (CONTINUED)
NON-SEISMIC INITIATION STsas Line B, sax No McRE SEVERE THAN SEISMIC EVENT Fesa LINS EReal No MoRE SEVERE THAN SEISMIC EVENT C0r4CLUSION:
2 OTSG FAILURE CASE WORST STEAM LINE 3REAK ACCIDENT FEED LINE BREAK ACCIDENT IS DIFFERENT FRCM FSAR.
ACCEFTABLE RESULTS ACHIEVEABLE 2.337
Q ACCIDENT ANALYSIS CONSIDERATIONS ST uM Ltys Bas w
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DNBR BEFORE TRIP - BOUNDED BY ', : MITIGATED ACCIDENT ANALYSIS 2.
HOT CHANNEL ANALYSIS - BOUNDED BY UNMITIGATED ANALYSIS WITH 2% SHUTDOWN M,4RGIN
- GOAL IS TO RETURN TO 13 SHUTDOWN MARGIN 3.
CONTAINMENT PRESSURE - BOUNDEL BY APP. 15B ANALYSIS 4.
CONTAINMENT TEMPERATURE - BOUNDED BY ANALYSIS BEING SUBMITTED ON 10/30/78 0
b ACCIDENT ANALYSIS CONSIDERATIONS Fsso LrNe Bos2K 1.
PRESSURIZER LEVEL - EXPECT ACCEPTABLE RESULTS 2.
RCS PRESSURE - EXPECT ACCEPTABLE RESULTS 3.
CONTAINMENT PRESSURE - BOUNDED BY STEAM LINE BREAK 4.
EMERGENCY FEEDWATER - FULL FLCW BEFORE FSAR ASSUMES :ULL FLC
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