ML20236L379
| ML20236L379 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/06/1998 |
| From: | Curry D AFFILIATION NOT ASSIGNED |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9807100332 | |
| Download: ML20236L379 (7) | |
Text
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PARSONS l
P Daniel L Curry, Vice President. Nuclear Sorwces Parsons Enwgy & Chqrnicals Group Inc 2675 Morgantown Road
- ihading. Pennsylvania 19607 * (610) 855-2366 + Fax: (610) 855-2602 l
July 6,1998 Docket No. 50-336 Parsons NUM2-PPNR-1685-L U.S. Nuclear Regulatory Commission Attention Document Control Desk Washington, D.C. 20555 Millstone Nuclear Power Station Unit No. 2 Independent Corrective Action Verification Procram (ICAVP)
Gentlemen:
Pursuant to your recent request, attached please find the Millstone Unit 2 ICAVP Bi-Weekly Report for week ending July 3,1998.
Please call me at (610) 855-2366 if you have any questions.
Sincerely, Daniel L. Curry Parsons ICAVP Project Director I
DLC:cvb Attachments 1.
Bi-Weekly Report
[
cc:
E. Imbro ('.) - USNRC j
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R. Laudenat - NNECo J. Fougere - NNECo Rep. Terry Concannon - NEAC Project Files i
9007100332 990706..
PDR ADOCK 05000336 P
PDR; PAGE1 Encompass p
PPNR1685. doc a
PARSONS Daniel L. Curry, ne Pwm f u.mw hces Parsons Energy & Chemicals Group inc 2675 Morgarrtown Roa,d e Reading Pennsylvania 19607 * (610) 855-2366
- Fax (610) 055-2602 July 6.1998 Doc. ID: NUM2-PPNU-1684-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 Unit 2 ICAVP for the week ending July 3,1998.
Meetings are planned with the NRC and NNECo this week to discuss the schedule for the remaining recovery activities, ICAVP reviews and NRC audits / inspections in order to develop an integrated plan for completion of Unit 2 ICAVP.
Tier 1 - System Vertical Slice Reviews AFW, RRC and EDG system reviews are targeted for discovery complete by July 31. This is exclusive of e
CAR, and DR close out.
The action items affecting the completion are contained on attachment entitled "OPEN RAls DUE DATES OF 6-16-98" The dates associated with discovery complete are intimately tied to these RAls.
It is essential that we receive NNECo date for implementation of the following programs:
EQ (EE-352-EQML, EE-332-Zones, Revised TRAs, EQ Reports)
HELB (Structural Analyses - EB, inside Containment Analyses)
SBO (Shutdown Scenarios, Calculations, EOP 2530)
Appendix R (FHA, Compliance Report, AOPs - updated for Appendix "R")
Completion of Tier 2 reviews will have a direct effect on the completion of Tier 1 activities.
Tier 2 - Accident Mitigation System Review Analysis Review - 29 Design Basis Events (DBEv):
e 16 DBEv Discovery Complete 3 DBEv Discovery Complete (Back check revised analyses in progress) 3 DBEv Discovery Complete (Back check revised design inputs / analyses for 3 Fuel Handling Accidents when received) 6 DBEv Validations in Progress (Need Revised Analyses for LBLOCA, SDLOCA & DBA) 1DBEv Validations in Progre:s (Need Design Inputs and Revised Analysis for SGTR)
Revised Design inputs are required for 3 radiological analyses (RAl-1573, RAI-1769).
e Reanalyses have been received for 9 of the 16 DBEv.
NNECo provided a schedule update on June 30,1998. This status is shown in Appendix B.
Discovery complete date is estimated as 3 weeks following receipt of revised analyses.
b
Mr. Richard Laudenat Northeast Nuclear Energy Company NUM2-PPNU-1684-I, July 6,1998 Tier 3 - Process Review Tier 3 resiew of change process samples is complete.
Review of Vendor Manual upgrade corrective actions has begun. A RAI has been issued for all of the Tier 3 review samples.
' Other Activities:
Phone conferences completed on June 23, 25,30 and July 2,1998.
1 Discrepancy Reports See Attachment A for details
'RAI (Status)
A total of 1778 RAl's have been issued. Details of outstanding RAI responses and partial responses are L
provided on Attachment C.
Should you 1. ave any questions on the contents of this progress report, do not hesitate to contact me at.
(610) 855-2366.
Sincerely, L
Daniel L. Curry Project Director DLC/cyb Attachment ec:
J. Fougere E. Imbro(USNRC)
E. A. Blocher M. J. Akins J. L. Caldwell
- W. L. Dobson R. T. Glaviano J. F. Hilbish Project Records 2 of 2 Encompass Letter PPNU1684. Doc
~
Attachment A to July 3,1998 Bi-weekly Report Discrepancy Report Summary and Status 676 Preliminary DR Numbers issued by Parsons 534 Preliminary DRs approved of which 18 determined to be invalid 200 Responses received to date from NU 43 DRs CLOSED 78 DRs OPEN 79 DRs IN-PROGRESS (Awaiting revised response from NU on 2 DR's)
Of the 43 Valid and Closed Discrepancies resolutions 19 Confirmed Discrepancies 13 Previously Identified by NNECo 11 Non-discrepant Conditions Of the 19 Confirmed Discrepancies 0 - Level 1 0 - Level 2 2 - Level 3 17 - Level 4
l Attachment B: Tier-2 AMSR Validation Open Items (Status as of 7/02/98)
This attachrnent lists information needed to complete validation of the Critical Design Characteristics associated with the FSAR Chapter 14 Accident Analyses.
l Preliminary Discrepancy Renorts - Provide completion schedule and closure package for the listed DRs.
DR-027 Enci Bldg Ventilation System (Parsons comments on NNECo response by 10 July) Rev DR-033 HPSI Flow (Open - Pending Status)
DR-045 Deboration During Startup (Closed as Confirmed Level 3)
Rev DR-202 MSSV Accumulation (Parsons comments on NNECo response by 8 July)
Rev DR-205 Pressurizer Safety Valve Accum.
(Parsons comments on NNECo response by 8 July)
Rev DR-412 Containment Purge Supply Air Flow Deficit NNECo identified items - Provide completion schedule and closure package for the listed items.
Note: the listed items may have related UIRs, CRs, etc.
UIR-288 RCS Pressure Uncertainty UIR-929 Pressurizer Level UIR-2601 Containment Purge Flow Rate Used in Fuel Handling Accident Analysis UIR-3198 Containment Purge Isolation Time Assumed for Fuel Handling Accident Revised FS AR Chanter 14 Analvses - The below table lists events being reanalyzed by NNECo and identifies information needs to complete the Tier-2 validation. RAls will be submitted upon NNECo acceptance of the revised analyses.
Eventi
. Design inputs'.
NNECo Acceptt LRevis_edj Analpsis(ECD)G
!Analysid 14:1.3? 5 Increase in' Steam Floivi J27 Feb 98 R6 Cersplete@M i30 Juh~98 RN x
l14:1-51 e Main Steam'Line Break ~(RCS -Analysish 127 Feb 98:Rt Combleteh n2 Jul 98 Rti 14:2ilt Rossof Extenial Load s 127 Feb 98'Rs
- Conibletel
?23 MaE98 IU 14.2:41 1 Closure of Main'Stcam Isolation Valve 2
'27 Feb'98 R4 Completei
>23' Mar:98 R2 i
114.2.71 sloss ofNormal Feedwater Flos L27 Feb 98 R$
Complete $
230 Jun 98 Rt l
- 14X11
? Startup RodWithdrawal Accident?
r24 Mar 98 R4 CompletR X19 Juh'98 R9 114.4.~63 (CVCS Malfunction Cansing RCS Deboration' 128 Abr98 RR lCompleteli
- 193dd 98 Ri l
14.6.5.1 Large Break LOCA (RCS Analysis) Apr 98 R$
31 Aug 98 RAI (later) l 14.6.5.2 Small Break LOCA 128 Apr98 R3 31 Jul 98 RAI(later) l 14.6.3 Steam Gen Tube Rupture - Mass Relcase Nhahd 6 Jul 98 RAI-1769 I
Steam Gen Tube Rupture - Radiological Calc RAI-1769 14 Aug 98 RAI (later) 14.7.4.2.1 Fuel Handling Accident in Spent Fuel Pool RAl-1573 14 Aug 98 RAI (later) l 14.7.4.2.2 Fuel Handling Accident in Containment 112 Jun 98 Rs 14 Aug 98 RAI (later) 14.7.5 Spent Fuel Cask Drop RAI-1573 14 Aug 98 RAI (later) l 14.8.2;13 i Containment' Analysis (MSLB)
. Received 1 Co'mpleter
'6 Mar 98 RF (14.8.2.1) Containment High Press Trip During MSLB
'28 Apr 98 RC 10 Jul 98 RAI (later) l
-14.8.2.25 > Containment' Analysis (LOCA)
Receivedi Completer 6 Mar 98 RS 14.8.4 Radiological-Design Basis Accident 12 Jun 98 R 14 Aug 98 RAI (later)
Partial K RC Pump Coastdown Curve '
c24 Mar 98 R7 Completel N/Af Note: R = Documents received by Parsons on indicated date
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