ML20247E859
| ML20247E859 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/08/1998 |
| From: | Curry D AFFILIATION NOT ASSIGNED |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUM2-PPNR-1431, NUDOCS 9805190015 | |
| Download: ML20247E859 (5) | |
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PARSONS Danlet L. Curry, Vice Pres dent. Nuclear Ecroces Parsons Energy & Chemicals Group loc.
2675 Morgantown Road + Reading. Pennsylvania 19607 e (610) 855-2366
- Tax: (610) 855-2602 May 8,1998 Docket No. 50-336 Parsons NUM2-PPNR-1431-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 Program (ICAVP_)
Gentlemen:
Pursuant to your recent request, attached please find the Millstone Unit 2 ICAVP Bi-Weekly Report for week ending May 1,1998.
Please call me at (610) 855-2366 if you have any questions.
Sincerely, 441 01tc Daniel L. Curry Parsons ICAVP Project Director DLC:cvb Attachments 1.
Bi-Weekly Report cc:
E. Imbro (2) - USNRC H. Eichenholz - USNRC R. Laudenat - NNECo J. Fougere - NNECo Rep. Terry Concannon - NEAC Project Files
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PARSONS Daniel L. Curry, w.e ruewent nuciear wces Parsons Energ/& Chemcals Group inc 2675 Morgantown Road
- Readir:g. Pennsylvania 19607 * (610) 855-2366
- Far (610) 855-2602 May 8,1998 Doc. ID. NUM2-PPNU-1430-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 May 1,1998.
Project Schedule: I have deleted the forecast for the discovery completion dates for Tier 1 and Tier 2 activities We are currently reevaluating the continuing schedule impact based upon the limited receipt of information on Unit 2. This reevaluation will include both the overall Unit 2 schedule and lessons teamed from Unit 2 ICAVP to date.
Tier 2 - Accident Mitigation System Review Reviewed Tier 2 validation methodology with NRC staff on April 28,1998.
e Closure of preliminary DRs, UIRs and RAls is required to complete Tier-2 review. See Attachment B for details.
Design inputs have been received for 11 of the 12 DBEv being reanalyzed by NNECo. Design inputs needed for Steam Generator Tube Rupture Radiological Analysis.
l Revised NNECo completion dates for the Chapter 14 accident reanalysis were provided to Parsons on i
April 30,1998. Parsons is evaluating the impact of the revised dates on the Tier 2 schedule.
Analysis review - 29 Design Basis Events (DBEv) 15 DBEs Discovery Complete 6 DBEv VeStions in Progress 8 DBEv Awaiting Revised Analyses Tier 3 - Process Review Preparations have been completed for the Tier 3 NRC inspection to start at Parsons on May 4,1998.
Five additional setpoint change requests have been added to the Ti:r 3 review due to the identification of 74 additional SCRs in the sample population.
Reviews completed for specification revisions and ASME Section XI Repairs.
Reviews in progress for drawing revision and NCRs based on RAI responses.
Vendor manua! review on hold until NNECo can identify the population of Unit 2 manuals to be updated l
and the NNElo schedule for updates and validation of procedures.
P I
l l
Mr. Richard Laudenat Northeast Nuclear Energy Company NUM2-PPNU-1430-L
(
May 8,1998 Other Activities:
Phone conferences completed on April 21,23,28 and 30,1998.
Discrepancy Reports See Attachment A for details l
RAI (Status) 1 Total issued 1480 e
38 greater than 2 weeks / total outstanding 74 e
l HPSI - (RAI-0766, RAI-0921, RAI-1054) e AFW - (RAl-0766, RAI-1087) l
=
RRC -(RAI-l125(p))
e EDG - (RAI-1223, RAI-1246(p), RAI-1293)
Tier 2 Validation (RAI-l115(p), RAI-1257(p), RAI-1314)
Tier 3 (RAl-1401, RAI-1412, RAI-1449, RAI-1427)
Should you have any questions on the contents of this progress report, do not hesitate to contact me at (610) 855-2366.
Sincerely, rca]
4 Daniel L. Curry Project Director DLC/cyb Attachment cc:
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 PPNU1430. Doc
Attachment A to May 1,1998 Bi-weekly Report Discrepancy Report Summary and Status 538 Preliminary DR Numbers issued by Parsons 437 Preliminary DRs approved of which 15 determined to be invalid 110 Responses received to date from NU 37 DRs CLOSED 56 DRs OPEN 17 DRs IN-PROGRESS (Awaiting revised response from NU on 2 DR's)
Of the 37 Valid and Closed Discrepancies resolutions e
16 Confirmed Discrepancies 12 Previously Identified by NNECo 9 Non-discrepant Conditions Of the 16 Confirmed Discrepancies 0 - Level 1 0 - Level 2 0 - Level 3 16 - Level 4 l
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e Attachment B: Tier-2 AMSR Validation Open Items (Status as of 4/30/98)
This attachment lists information needed to complete validation of the Critical Design Characteristics associated I
with the FSAR Chapter 14 Accident Analyses.
Preliminary Discrepancy Reports - Provide completion schedule and closure package for the listed DRs.
DR-027 Enclosure Building Ventilation System DR-033 HPSI Flow DR-045 Deboration During Startup DR-202 MSSV Accumulation DR-205 Pressuri7er Safety Valve Accumulation DR-313 RPS RC Low Flow Trip Setpoint (NNECo response received. Parsons review in progress) (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 FSAR Chapter 14 Analyses - The below table lists events being reanalyzed by NNECo and identifies l
information needs to complete the Tier-2 validation. RAls will be submitted upon NNECo acceptance of the revised analyses.
Event -
Design Inputs i NNECo Accepti Resised l
Analysis (ECD)!
Analysis 14.1.3 Increase in Steam Flow 27 Feb 98 RM 15 Jun 98 RAI (later) 14.1.5 Main Steam Line Break (RCS Analysis)
- 27 Feb 98 R$
15 Jun 98 RAI(later)
!14.2.1 M tLoss of External Loads
- W f27 Feb 98'RT Complete? - E 223 Mar 98 Rs 14.'2.41 s J Closure of Main Steam Isolation Valv6 i27 Feb 98 Rt CampleteMf
- 123 Mar 98 RS 14.2.7 Loss of Normal Feedwater Flow 227 Feb 98 R4 15 May 98 RAI(later) 14.4.1 Startup Rod Withdrawal Accident 24 Mar 98 R7 15 May 98 RAI(later) 14.4.6 CVCS Malfunction Causing RCS Deboration ?28 Apr 98 Rig 15 May 98 RAI (later) 14.6.5.1 Large Break LOCA (RCS Analysis)
-28"Apr:98 Rs 15 Jun 98 RAI(later) 14.6.3 Steam Generator Tube Rupture RAI-ll15 15 May 98 RAI(later)
J14.8 2;lh Contamment' Analysis (MSLB)?
.Receised 0 Complete #
16 Mar 98 R41 (14.8.2.1) Containment High Press Trip During MSLB J28'Apr 98 Rt 15 May 98 RAI (later) 14.8.2.22 8 Containment Analysis (LOCA)B Received Complet6iim a !6' Mat 98 Ris RC Pump Coastdown Curve
- 24 Mar 98 R4 1 May 98 RAI (later)
Note: R = Documents received by Parsons on indicated date Reauests for AdditionalInformation RAls: 1257 & 1314 i
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