Text

Forwards Millstone Unit 2 Independent Corrective Action Verification Program bi-weekly Rept for Week Ending 980320. W/Summary Schedule
	ML20216J726
Person / Time
Site:	Millstone
Issue date:	03/20/1998
From:	Curry D; External (Affiliation Not Assigned)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9803240056
	Download: ML20216J726 (9)
	v • d • e

" PARSONS Daniel L Curry, vpe Presr>ent, tavcisar Sorvices Parsons Energy & Cnemicals Group Inc.

2075 Morgantown Road

Reading. Pennsylvania 19007 * (610) 855-2366

Fast (610) 855-2602 March 20,1998 Docket No. 50-336 Parsons NUM2-PPNR-1263-L U.S. Nuclear Regulatory Commission Attention: Document Control Desk l

Washington, D.C. 20555

(

Millstone Nuclear Power Station Unit No. 2

[rldepenAnt Corrective Action Verification Program (ICAVP)

Genticmen:

Pursuant to your recent request, attached please find the Millstone Unit 2 ICAVP Bi-Weekly Report for week ending March 20,1998.

Please call me at (610) 855-2366 if you have any questions.

Sincerely, j

Daniel L. Curry Parsons ICAVP Projcct irector 1

DLC:cvb Attachments 1.

Bi-Weekly Report 2.

Summary Schedule

/

cc:

E. Imbro (2j - USNRC

/

11. Eichenholz - USNRC R. Laudenat - NNECo J. Fougere - NNECo Rep. Terry Concannon - NEAC 2# /

Project Files I

9803240056 980320 PDR ADOCK 05000336 P

PDR s.

rpm

..auase PAGE1 Encompass g

PPNR1263. doc 4

' PARSONS Daniel t Curry, Vye Prescent. Nuclear Services ParsonsErergy & Cnemicais Group inc.

2675 Morgantown Road + Reading, Pennsylvania 19607 + (610) 855 2366 + Far (610) 855-2002 March 20,1998 Doc. ID: NUM2-PPNU-1262-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 March 20,1998.

Project Schedule: Schedule (Refer to Attachment C)

Tier 1 - System Vertical Slice Reviews AFW system review is moving forward with receipt of new information. However, progress will be e

limited pending receipt of revised analysis.

Programs associated with EQ, HELB, SBO, Appendix "R" are on-hold pending receipt ofinformation of EQ zones. Current information indicates:

=> SB0 target date - end ofMarch.

=> Appendix "R" - some information has been provided and is being reviewed.

=> HELB/EQ - limited information will be available from NNECo by mid-May, final infonnation is expected mid-November. Schedule options associated with this change are being evaluated.

Tier 2 - Accident Mitigation System Review Closure of preliminary DRs, UIRs and RAls is required to complete Tier-2 review. See Attachment B for e

details.

Design inputs have been received for 7 of the 12 DBEv being reanalyzed by NNECo. Design inputs for the rernaining 5 BBEv are scheduled to be transmitted to Parsons by April 15,1998. -NNECthas indicated to Parsons that the accident analysis design inputs and reanalysis schedule may be extended. We are evaluating the potential to adjust Tier 2 resources downward in these areas while still maintaining the overall ICAVP schedule for Unit 2. The Tier 2 schedule will be revised to address the revised dates for receipt of design inputs, and the resource loading question, in the next bi-weekly update.

Analysis review - 29 Design Basis Events (DBEv) 27 DBEv Analyses Reviewed 9 DBEv Validations in Progress 8 DBEv Discovery Complete b

1 Mr. Richard Laudenat Northeast Nuclear Energy Company NUM2-PPNU-1262-L March 20,1998 -

Tier 3 - Process Review Tier 3 discovery complete date remains April 8,1998 with exception of vendor technical information e

reviews.

Report preparation in progress for completed sample areas.

Reviews in progress for specification revision, drawing revision, NCRs and EWRs.

Millstone input to Parsons on Unit 2 vendor manuals to be updated prior to restart and the schedule for the update remains outstanding.

Response to Tier 3 RAls within the next week is important to completing discovery by April 8,1998.

Other Activities:

Phone conferences completed on March 10,12,17 and 19,1998.

Discrepancy Reports See Attachment A for details RAI (Status)

Totalissued 1264 e

41 greater than 2 weeks / total outstanding 79 Tier 1 Topical Areas (RAI-l105)

=

AFW Calculations (RAI-1086)

Tier 2 Design inputs (RAI-l115) e Tier 3 (RAI-l168, RAI-I176, RAI-l184, RAI-l196, RAI-1219, RAI-1221, RAl-1230) e Should you have any questions on the contents of this progress report, do not hesitate to contact me at (610) 855-2366.

Sincerely, Daniel L. Curry Project Director DLC/ctb Attachment cc:

. J. Fougere W. L. Dobson E. Imbro (USNRC)

R. T. Glaviano

- E. A. Blocher J. F. Hilbish M. J. Akins Project Records J.

L. Caldwell 2 of 2 Encompass Letter PPNU1262. Doc

4

' Attachment A to March 20,1998 Bi-weekly Report Discrepancy Report Summary and Status 472 Preliminary DR Numbers issued by Parsons 383 Preliminary DRs approved of which 15 determined to be invalid 98 Responses received to date from NU 34 DRs CLOSED 57 DRs OPEN 07 DRs IN-PROGRESS (Awaiting revised response from NU on 5 DR's)

Of the 34 Valid and Closed Discrepancies resolutions e

15 Confirmed Discrepancies 11 Previously Identified by NNECo 8 Non-discrepant Conditions Of the 15 Confirmed Discrepancies 0 - Level 1 0 - Level 2 0 - Level 3 15 - Level 4 i

4 Attachment B: Tier-2 AMSR Validation Open items (Status as of 3/20/98)

This attachment lists information needed to complete validation of the Critical Design Characteristics associated 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 Pressurizer Safety Valve Accumulation (New Item)

DR-313 RPS RC Low Flow Trip Setpoint 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 Revised FS AR Chanter 14 Analyses - The below table lists events being reanalyzed by NNECo and identifies information needs to complete the Tier-2 validation.

Event Design NNECo Accept -

Revised :

Inputs -

Analysis (ECD) '

Analysis 14.1.3 Increase in Steam Flow

27 Feb 98 Rs 15 Apr 98 RAI(later) 14.1.5 Main Steam Line Break (RCS Analysis)

27 Feb 98 R9 15 Apr 98 RAI(later) 14.2.1 Loss of External Load 27 Feb 98 RS -Completei RAI-1128 14.2.4 Closure ofMain Steam Isolation Valve

27 Feb 98 R4 Conspletei RAI-1128 14.2.7 Loss of Normal Feedwater Flow 127 Feb 98 R; 31 Mar 98 RAI(later) 14.4.1 Stanup Rod Withdrawal Accident RAI-l115 15 Apr 98 RAI(later) 14.4.6 CVCS Malfunction Causing RCS RAI-l115 30 Apr 98 RAI(later)

Deborrtion 14.6.5.1 Large Break LOCA (RCS Analysis)

RAI-l115 30 Apr 98 RAI(later) 14.6.5.2 Small Break LOCA RAI-l115 15 Apr 98 RAI(later) 14.6.3 Steam Generator Tube Rupture RAI-l115 31 Mar 98 RAI(later) 14.8;2.1 3 Cordainment ^ Analysis (MSLB)1 Receivedc

. Interim i

6 Mar 98 R1 (14.8.2.1) Containment High Pressure Trip During RAI-l115 15 Apr 98 RAI(later)

MSLB 14:8;2.29 Containment' Analysis (LOCA);

Received 6

~ Co~mplete:1 6 Mar 98 RN RC Pump Coastdown Curve RAI-l115 15 Apr 98 RAI(later)

Note: R = Documents received by Parsons on indicated date B.eauests for AdditionalInformation None

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Dear Mr. Laudenat:

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