ML20198G178
| ML20198G178 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 11/18/1974 |
| From: | Cox T US ATOMIC ENERGY COMMISSION (AEC) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-1017 NUDOCS 8605290267 | |
| Download: ML20198G178 (5) | |
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! DOCKET NOS: 50-460 and 50-513
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i APPLICANr: WASHINGit]N PUBLIC POWER SUPPLY SYSTDI (WPPSS)
FACILITY: WASHINGlUN NUCLEAR ONE AND RJUR (WNP-1, 4)
SIMIARY OF MEETING HELD 10 DISCUSS CONTAISIENT SYSTB1S DESIGN AND ANALYSIS On October 11, 1974, repusentatives of WPPSS, United Engineers and l
Constructors (UE6C), Babcock and Wilcox (BSO, and the Regulatory staff met in Bethesda, Maryland, to discuss staff concerns regarding containment systems. The concerns involved infomation needed by the Containment Systes Branch (CSB) staff in order to prepare CSB input to the Safety Evaluation Report, which input is currently scheduled for completion on
- November 15, 1974. An attendance list is enclosed. A stenary of the meeting discussion follows.
Staff position no. 6.75* was briefly discussed by W. Pasedag of the staff.
A WPPSS comitment to perform the necessary preoperational proof test was made. This committment and a preliminary description of the test will be included in a forthcoming amendment to the PSAR. The test will involve operation of the containment spray ptznps, with simultaneous flow to the plaip suction from both the borated water storage tank and the sodium hydroxide tank. Tank levels or changes in level will be measured at
- l. : selected time intervals. Additive concentrations will be computed from l'- tank level measurements and verified by chemical analysis of samples taken from the mixed flow. Liquids used in the test will simlate the viscosity and density of the actual borated water and soditan hydroxide.
l l The staff position no. 6.72* regarding =v4== allowable pli (less than or equal to 11.0) of the containment spray solution was discussed. W. Pasedag
' explained that syst e designs and subsequent staff evaluations to date have been based on corrosion rate and magnitude data that, in the staff's judgement, will support a =vi== allowable #1 of 11.0. Use of solutions which at any time have pil greater than 11.0 will require detailed analytical justification, l including as a mini == the presentation of corrosion data for the higher pil j solution. Since the staff has presented its position in this matter and t
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I *IArtter to J. J. Stein (WPPSS) from A. Schwencer dated 9/13/74 .
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j WPPSS Meeting Stamary ,
is in the process of writing safety evaluation report input, additional review of the spray system to justify a I fi of greater than 11.0 may l
result in a delay in empletion of the staff aview in the contminmant spray systen area. h applicant decided to consider this issue further prior to response to the staff position (due to the staff on October 21, 19741 j
1 WPPSS stated that they would plan to operate contai==nt sprays as necessary in the post-IIX:A environment, to assure adequate mixing of any hydrogen produced. His cemittment was sought by the staff since the contm4= ant 1
fan coolers are not Category I equipment and may not be considend availablo for contalment atmosphere mivig prior to activation of the containment purge system.
Several hours were spent in analyzing the differences between contai-t i
pressure calculations done by the staff and those done by E4C. %e staff's I
emien1=tions show that the dotble-ended pump suction break (11.17 ft2 ana) with asstsuptions of full BCCS operation and no steam condensation nsults
- in tbs highest containment pressure. 'Ihe staff calculations result in an uiw.cogsbly low design margin at 200 seconds after the IDCA event, with the pressure still increasing slightly. Mass and energy input data for times past 300 seconds was not av=41=hle in the PSAR when the calculation was
! dona.
' However,2 ESC calculations show the highest pressure case to result frtm a 15.75 ft hot leg break. Purther, W4C calculated pressum was i decxuasing after 200 seconds. It was finally concluded that additional l calculations would be needed to resolve the apparent differences between i
the staff's calculational techniques and those of El.C. E6C will perform these calculations during the week of October 14, 1974. Purther staff
- and/or applicant actions will be based on the comparison of the calculations.
i Q..'ykdMkb i 'Ihans Cox, Project Manager i
Light Water Reactors Branch 2-3 Directorate of Licensing
Enclosure:
l Attendance List i
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orrecs , LWR 2-3 ouanaus, Ox W , . , , , , , . ,,
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4 Form AEC.)t8 (Rev. 9 53) AECM 0240 W u. e. novsanusut paintime orricas sera.sss.ies
i ATIENDANCE LIST DOCKETS 50-460 AND 50-513 ,
bEETING WIni hPPSS WASHINGTON NUCLEAR mli AND FQJR October 11, 1974 AEC T. Cox W. Pasedag*
T. G mene*
. WPPSS A. Hosler C. B. Organ UESC A. J. Friedman J. A. Daniel K. K. Niyogi J. M. Foremny V. Mania P. Karousakis B4W K. C. Shich K. E. Suhrke
- Denotes part-time attendance 4
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DOCKET NOS: 50-460 and 50-513 APPLICAYr: NAS!!ING10N PUBLIC POWER SUPPLY SYSTEM (WPPSS)
FACILITY: WASHINGTON NUCLEAR ONE AND RXJR (WNP-1, 4)
SibMARY INKN6WTION AND POSITIONS OF FEETING IIELD TO DISCUSS DRAFT ELECIRIcAL SYSTBtS REQUESIS GiaOctdow 30, 1974, representatives of WPPSS, United Engineers and l
i Constructors (UEGC), Babcock and Wilcox (B5W) and the Regulatory staff met in Bethesda, Maryland, to discuss the subject draft requests and positions pre Branch (EICSB) .
pared The purpose by the Electrical of the discussion Instrumentation and Control was to assure that theSystems applicant understands the concerns of the staff and to hear preliminary responses to specific issues. An attendance list is enclosed. A surmary of the meeting discussion follows:
I Fifty draft mquests and postions were discussed and six additional i
ones were presented to the applicant at the meeting. The draft material discussed is scheduled to be fomally issued to the applicant by the staff on November 20, 1974.
i Sevoral areas of disagnsE between the staff and applicant surfaced i
during the discussions. One such area involves the staff position requiring applicant compliance with IEEE-323-1974. B.91 stated that they would have to take exception to the aging requirements of the new standard, and that they were attempting to schedule a generic meeting with the staff on this subject expected to take place in early December i
' 1974. Other staff positions to which the applicant felt they might take exception in their responso were:
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- 1) The staff position that safety m1ated instrtmentation records i shall be seismically qualified to accurately record after
! (but not during) a seismic event.
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- 2) The staff position that fully automatic switchover from the l- t'.
ECCS injection made to the recirculation mode must be pmvided iu in conformance with IEEE 279-19 71. B4W believes that the WPPSS U system design provides for few enough requimd operator actions and a long enough time period in which to accomplish that switchover, such that adequate system safety is provided with manual switching.
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yorm AEC 318 (Rev. p.33) AECM 0240 1lt u. e. sovsma'asest raiaT'"* *FF'888 8*.ese s ee
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ATTENDANCE LIST MEETING WITH WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET N'1S. 50-460 & 50-513 WASHINGTON NUCLEAR ONE AND FOUR OCTOBER 30, 1974 Atomic Energy Commission United Engineers & Contractors T. H. Cox J. R. Schmieder R. A. Scarano A. J. Friedman yppgg J. G. Kritikson J. A. Cannon N. S. Porter J. P. Thomas E. P. Rothong G. L. Waldkoetter A. G. Hosier B&W D. C. Winterich A. F. McBride R. J. Brockman E. S. Patterson K. e. Suhrke J. E. Prioletti
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