ML20203E130
| ML20203E130 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 02/20/1998 |
| From: | Curry D AFFILIATION NOT ASSIGNED |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUM2-PPNR-1145, NUDOCS 9802260268 | |
| Download: ML20203E130 (9) | |
Text
PARSONS Daniel L Curty,vosr.e4 er* A m e W es s' arum i t>nrut L O ~u. : Wcup sna P075 Margantown P..., e 4eadng h tvisvivania 19607 * (610) 8% 23f4
- Ias (610) 8% NO2 February 20,1998 Docket No 50 336 Parsons NUM2 PPNR il45-L U.S. Nuclear Regulatory Commission Aitention: Document Control Desk Washington, D C. 20555 Millstone Nuclear Power Station Unit No. 2 IndependynLContcliitAcijon VerifiSation Progntm. (ICAVE)
C;ntlemen:
Pursuant to your recent request, attached please find the Millstone Unit 2 ICAVP Bi Weekly Report for week ending February 20,1998.
Please call me at (610) 855 2366 if you have any questions.
Sincerely, ul/
Daniel L. Curry f8FParsons ICAVP Project Director DLC:ctb Attachments 1.
Bi Weekly Report 2.
Summary Schedule l
\\
cc:
E. Imbro (2)- USNRC
- 11. Eichenholz USNRC R. Laudenat - NNECo J. Fougere - NNECo kd -
Rep. Terry Concannon NEAC Project Files
',nI Wil l.il.11llll ll 9802260260 930220 v..
PDR ADOCK 05000336 P
PDR PAGEI Encompass
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PPNRll45. doc
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RARCONO Daniel L Curty, v<e em.aet Iww Smu Parscris Enoegy & Cr.onacats Group tre P675 Mygantown noad
- Reading Pennsytvania 19607 * (610) 855-2366
- rav (610) 855 2602 February 20,1998 Doc. ID: NUh12 PPNU.!!44 L Mr. Richard Laudenat Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 2 P. O. Box 128 Waterford, CT 06385 Re:
Millstone Unit 2 ICAVP Bi Weekly Progress Report
Dear Mr. Laudenat:
The following represents a bi weekly progress report for work completed on Millstone Umt 2 ICAVP for the week ending February 20,1998.
Project Schedule: Schedule (Refer to Attachment C)
Tier 1 System Vertical Slice Reviews liPSI report information is approximately 95% complete.
e Revised Form 7 in PI 01 to improve efficiency in modification review based on liPSI experience.
e Personnel are starting to be shifted from 11 PSI to the EDO and RRC systems.
AFW system is still on hold pending response to recent RAls requesting the design input information necessary to detennine the design basis for the system.
Prograrns associated with EQ, !!ELB, SHO, Appendix 'R" are on hold pending receipt ofinfomiation of EQ zones. Current information indicates.
o SB0 target date end of March
=> Appendix "R" target date - mid March
=> llELB/EQ before restart, no date System completion dates remain unchanged with Final Report issuance scheduled for July 10,1998.
Tier 2 - Accident Mitigation System Review Tier 2 Report date remains as April 28,1998.
Analysis review. 29 Design Basis Euntt (DBEv) 26 DBEv Analyses Reviewed 17 DBEv Validations in Progress Completed review of" Decrease in P.C Flow" events.
Closure of preliminary DRs and UIRs is required to complete Tier-2 review. Also,12 DBEv are being reanalyzed by NNEco. See Attechment D for details.
b
Mr. Richard Laudenat Northcast Nuclear Energy Cornpany NUM2 PPNU-l144.L February 20,1998 Tier 3 Process Review Tier 3 Report preparation date remains April 8,1998, issuance of the report is dependent on DR e
lesolution.
Report prcparation in progress for completed sample areas.
1.icensing Document Change sample evaluation is in final Parsons review and approval.
Reviews in progress for specification revision, drawing revision, NCRs and EWRs.
Millstone *. cdule for VT1 corrective action remains oetstanding.
Other Activities:
]
Phone conferences completed on February 10,12,18 and 19,1998 NRC Commissioners Driefing completed on February 19,1998 e
ICAVP status meeting completed on February 11,1998 (public meeting) e Discrepancy Reports See Attachment A for details RAI (Status and Significant items)
Totalissued 1127 22 greater than 2 weeks / total outstanding 74 e
Tier i Topical Areas (646 partial) e Tier 2 Reanalysis Design inputs (1115 partial) and Completed Analysis (1115, i128) e Tier 3 1068,1032 (Section Al sample review) e Should you have any questions on the contents of this progress report, do not hesitate to contact me at (610) 855 2366.
Sincerely, sEM i. Daniel L Curry
(
Project Director DLC/ctb Attachment cc:
J. Fougere W. L. Dobson E. In bro (USNRC)
R. T. Glaviano E. A. Blocher J. F. Ililbish M. J. Akins Project Records J. L. Caldwell 2 of 2 Encompass Letter PPNU) 144. Doc
1 l
Attachment A to February 20,1998 Ill-weekly report Discrepancy Report Summary and Status 417 Preliminary DR Numbers issued by Parsons 286 Preliminary DRs approved of which 8 deterrnined to be invalid
- 92 Responses received todate from NU 29 DRs CLOSED 57 DRs OPEN 05 DRs IN-PROGRESS (Awaiting revised response from NU)
- Of the 29 Valid and Closed Discrepancies resolutions 11 Confirmed Discrepaneles 11 Previously Identified by NNECo 7 Non-discrepant Conditions Of the 11 Confirmed Discrepancies 0 - Level 1 0 - Level 2 0 - Level 3 11 - Level 4
Attachment H: Tier-2 AMSR Validation Open items (Status as of 2/id/98)
This attachment lists information needed to complete validation of the Critical Design Characteristics associated with the FSAR Chapter 14 Accident Analyses.
Preliminary Discrepancy Reppfla - Provide completion schedule and closure package for the listed DRs.
l DR 027 Enclosure Building Ventilation System i
DR 033 IIPSI Flow DR 045 Deboration During Startup DR 202 MSSV Accumulation DR 313 RPS RC Low Flow Trip Setpoint 2
NNECo identiftcdlicms Provide completion schedule and closure package for the listed items.
Note: the listed items may have related UlRs, CRs, etc.
UIR 288 RCS Pressure Uncertainty UIR 929 Presrurizer I.evel hviscd FSAR Chapler 14 Ana]ncs The below table lists events being reanalyzed by NNECo and identifies information needs to complete the Tier-2 validation.
Event Design inputs NNECo Accept Revised -
Analysis (ECD)
Analysis 14.1.3 Increase in Steam Flow RAi 1115 31 Mar 98 RAI(later) _
14.1.5 Main Steam Line Break (RCS Analysis)
_14.2.1 Loss of External Load RAl1115 15 Feb 98 RAI-l 128 14.2.4 Closure of Main Steam Isolation Valve RAI l115 15 Feb 98 RAI l128 14.2.7 Loss of Normal Feedwater Flow RAIL 115 28 Feb 98 RAI(later)
(14.3.1) - RC Pump Coastdown Curve RAl-1115 28 Feb 98 RAI (late.r)_
14.4.1 Startup Rod Withdrawal Accident RAl-1115 28 Feb 98 RAIvater; 14.4.6 CVCS Malfunction Causing RCS RAI l115 30 Apr 98 RAI(later)
Deboration 14.6.5.1 Large Break LOCA (RCS Analysis)
RAI l115 31 Mar 98 RAI (later)
J.6.5.2 Small Dreak LOCA RAI-l 115 31 Mar 98 RAI(later) 14.6.3 Steam Generator Tube Rupture RAI-l 115 15 Mar 98 RAI (later) 14.8.2.1 Containment Analysis (MSLB)
Received Complete RAI-l115 (14.8.2.1) Containment liigh Pressure Tr:p During RAl.1115 28 Feb 98 RAI (later)
MSLB' 14.8.2.2 Containment Analysis (LOCA)
Received Complete RAI-l115
& quests for AdditionalInformation None
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