ML20198G570
| ML20198G570 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 01/06/1977 |
| From: | Cox T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-1137 NUDOCS 8605290673 | |
| Download: ML20198G570 (5) | |
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S F OC G77 i
Docket Ilos. 50-460 and 50-513 B
i APPLICNIT: Washington Public Power Supply System (WPPSS)
FACILITY: WitP-1, 4 i
SUBJECT:
SU!+1ARY OF HEETIiiG TO DISCUSS REQUIREMEilTS Ofl COMP 0 tie!iT C00LI!1G WATER SUPPLY TO REACTOR COOLNIT PUMPS On December IS,1976, representatives of WPPSS and the ilRC staff met to discuss WPPSS' proposed response to a staff position concerning cocponent cooling water requirements. This position was presented to i
WPPSS in a staff letter (O. Parr to J. J. Stein) dated October 19, 1976.
WPPSS asked for this meeting to apprise the staff of their intended response and to solicit the staff's peeliminary assessment of the WPPSS proposal. A meeting attendance list is enclosed.
WPPSS proposed to provide an automatic, safety grade reactor shutdown through the Reactor Protection System, on a reduction in component cooling water (CCH) flow as sensed in a section of the CCW return line which is cormon to all four reactor coolant punps. Reactor trip would be initiated on a flow decrease representing a loss of flow to at least two reactor coolant pumps. A five-minute tir.e delay would be incorporated in the trip. The WPPSS proposal did not include the comitment that the CCW systen supplying the reactor coolant pumps would be Seismic Category., Quality Group C (Regulatory Guide 1.26).
Staff cocInent on the WPPSS proposal is summarized in the following items:
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1.
The automatic. " safety grade" reactor trip proposed must be initiated by a loss of CCW to only one reactor coolant pump.
2.
The reactor trip function must be accouplished with systems and components designed to the requirements of IEEE-279 and other applicable safety class requirements. While the proposed design
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approach appears acceptable, there is some staff doubt regarding the details of the proposed method of flow sensing and signal input i
to the RPS system.
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DATS V Form AEC-318 (Rev. 9 53) AECM 0240
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ystem and components thereof supplying the reactor coolant j
pumps must be designed and constructed to Quality Group C requirements,
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'but will not be required to meet Seismic Category I requirenents.
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Acceptable reactor coolant pump operation must be demonstrated during the five minute. delay period after the loss of CCW is sensed.
j Such a demonstration must include some test data in combination with an analysis, rather than by analysis alor.e.
During the discussion S. Israel of tho staff noted that the requirement to initiate protective action on the loss of CCW to only one reactor coolant pump derives from the staff's position that a single active failure or operator error is an anticipated operational occurrence and shall not result in fuel damage. Further, accidental failures such l
as line breaks, considered to be infrequent incidents, shall not result i
in excessive fuel damage. 10 CFR 100 is the goveming criteria in limiting the consequences of such accidents.
i In a discussion of the CCW system design and quality assurance requirements, BSW representatives stated that pump and motor c0olers were designed to withstand earthquake loads, but'were not " qualified" Seismic Category I components by llRC standards, since not all the quality assurance requirements of the ASME Code were met.
l Following the meeting, members of the staff met to discuss the applicant's l
proposal of Quality Group D piping to the reactor coolant pumps on the basis that automatic protection would be provided for the plant. The staff's conclusion resulted in agreement with the applicant that Quality Group D piping was sufficient rather than the Quality Group C j
classification proposed by the staff provided the entire detection and j
protection system met all the requirements of safety grade equipment.,
l Also following the meeting, the staff concluded that when or if the loss l
of CCW is due to a postulated pipe crack or other accident (unanticipated occurence), the automatic protection system proposed by WPPSS may respond to a sensed loss of CCW flow equivalent to that normally supplied to two_._ __ __
i or more reactor coolant pumps. The system proposed must, however.
l automatically protect against a breach of the reactor coolant system ~
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pressure boundary, which would result from a loss of CCW flow to even one pimp. The basis for this conclusion is that the postulated T.rCr~'
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accident 'Ts considered ~an infrequent, iin5nt'icipated incident
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which coulFresult in at most a single locked ~ rotor.~~For this~ kind ~of
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event, limited fuel damage is acceptable, within the guidelines of i
10 CFR Part 100. The consequences of a single locked rotor have been 099,C. >
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analyzed in Section 15.0 of the SAR and found to be acceptable. Ilowever, i
a postulated crack or accident which could cause a multi-pump locked l
rotbr accident is not acceptable since it may result in excessive fuel damage or primary system pressures.
OT! tn:1 S!gned y 8
O. D. Eart_,g l
T. Cox, Project Manager
- Light Water P.cactors Granch Ho. 3 Division of Project Management
Enclosure:
As Stated f
cc: llashington Public Power Supply System ATTN: Mr. J. J. Stein i
ffanaging Director P. O. Box 93 i
3000 Caorge Washington llay Richland, Washington 99352 f
Mr. J. R. Schmieder United Engineers & Constructors, Inc.
30 South 17th Street Philadelphia, Pennsylvania 19101 Joseph B. Knotts, Jr., Esq.
Conner & Knotts 1747 Pennsylvania Avenue,II. W.
Washington, D. C.
20036 h
Mr. E. G. Ward
. Senior Project Manager
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Babcock & Wilcox Company P. O. Box 2160 Lynchburg, Virginia 23505 l
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- u. s. oovummusar palNTING OFFICE 8 98,4 986 988
EliCLOSURE ATTEllDAllCE LIST i
l 12/15/76 MEETIrlG OF WPPSS A10 flRC STAFF flRC T. Cox
- 5. Israel l
F. Ashe i
W. LeFaye UESC W. Gibson J.11111 V. Mani i
T. Richardson A. Friedman i
B. liemroff j
H. Pai i
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A. McBride j
W. Starkey J. Happell R. Brockman i
H. Baker
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A. Hosler
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Form AEC.318 (Rev. 9-53) AECM 0240 W u. s. oOVEAMMENT Pit lNTING OFFICE 81974 826-lee
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MEETING
SUMMARY
DISTRIBUTION lDocket File NRC PDR D. Ross Local PDR R. Tedesco TIC J. Knight ACRS (16)
S. Pawlicki IE (3)
I. Sibweil 0 ELD P. Check NRR Reading T. Novak LWR-3 File Z. Rosztoczy B. Rusche V. Benaroya E. Case G. Lainas R. Boyd T. Ippolito R. DeYoung V. Moore V. Stello R. Vollmer D. Skovholt M. Ernst J. Stolz W. Gammill K. Kniel G. Knighton
- 0. Parr B. Youngblood D. Vassallo W. Regan R. Clark D. Bunch T. Speis J. Collins P. Collins W. Kreger C. Heltemes R. Ballard R. Houston M. Spangler S. Varga J. Stepp J. Miller L. Hulman F. Williams H. Smith R. Heineman M. Rushbrook (3)
H. Denton Project Manager - T. Cox D. Muller NRC Participants W. Butler
- 5. Israel F. Ashe W. LeFave 6
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