Text

Forwards Millstone Nuclear Power Station Unit 2 Independent Corrective Action Verification Program bi-weekly Rept for Wk Ending 980306
	ML20216E852
Person / Time
Site:	Millstone
Issue date:	03/09/1998
From:	Curry D; External (Affiliation Not Assigned)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUM2-PPNR-1218, NUDOCS 9803180186
	Download: ML20216E852 (9)
	v • d • e

"

PARSONS Daniel L Curry, Vice Pressdent. Nuclear Serwces Parsons Energy & Chernicals Group inc 2675 Morgantown Road

Reading, Pennsylvania 19607 * (610) 855-2366

Fax: (610) 855-2602 March 9,1998 Docket No. 50-336 Parsons NUM2-PPNR-1218-L U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Millstone Nuclear Power Station Unit No. 2 Indcoendent 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 March 6,1998.

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

Sincerely,

/

Daniel L. Curry Parsons ICAVP roject Director DLC:cvb Attachments 1.

Bi-Weekly Report 2.

Summary Schedule cc:

E. Imbro (2) - USNRC f

i It Eichenholz - USNRC R. Laudenat - NNECo Ob

/

J. Fougere.NNECo Rep. Teriy Concannon - NEAC Project Files L

9803180186 980309 '*

MIEl.lE.lili.llE.E,1llllI PDR ADOCK 05000336 P

PDR.

I PAGE1 Encompass p

PPNR1218. doc

PARSONS Daniel L. Curry, %ce Prescent Nuclear Services

, Parsons &nergy & Chemicals Group Inc.

2675 Morgantown Road e Reading. Pennsylvania 19607 = (610) 855-2366 Fax: (610) 855-2602 March 9,1998 i

Doc. ID: NUM2-PPNU-1217-L Mr. Richard Laudenat Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 2 P. O. Box 128 Waterford, CT 06385 Re:

Millstone Unh 2 ICAVP Bi-Wc-k!y 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 6,1998.

Project Schedule: Schedule (Refer to Attachment C)

Tier 1 - System Vertical Slice Reviews HPSI report information is approximately 97% complete.

Some AFW system design input information has been received - will be reviewing calculations.

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

=> SBO target date - end of March

=> Appendix "R" target date - mid-March

=> HELB/EQ before restart, no date System completion dates remain unchanged wit!. Final Report issuance scheduled for July 10,1998.

RRC and EDG currently 11% complete. The significant number of calculations associated with RRC identified for changes will have an effect on progress and potentially schedule.

Tier 2 - Accident Mitigation System Review Tier 2 discovery complete April 17,1998, with exception of accident reanalysis reviews.

Analysis review - 29 Design Basis Events (DBEv) 26 DBEv Analyses Reviewed 1I DBEv Validations in Progress j

6 DBEv Discovery Complete l

Closure of preliminary DRs, UIRs and RAls is required to complete Tier-2 review. Also,12 DBEv are being reanalyzed by NNECo. See Attachment B for details.

1

i.

Mr. Ri hard Laudenat Northeast Nuclear Energy Company NUM2-PPNU-1217-L March 9,1998 i

Tier 3 - Process Review i

Tier 3 discovery complete date remains April 8,1998 with exception of vendor technical information reviews. Issuance of the report is dependent on DR resolution.

Report preparation in progress for completed sample areas.

Licensing Document Change sample evaluation was completed during this report period.

j 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 e

l update remains outstanding.

Other Activities:

Phone conferences completed on February 24,26 and March 5,1998 ICAVP status meeting completed on March 3,1998 (public meeting)

Discrepancy Repons

. See Attachment A for details l

l RAI (Status)

Totalissued 1201 e

26 greater than 2 weeks / total outstanding 63 e

l Tier 1 Topical Areas (646 - partial)

AFW Calculations (RAI-1086) l

]

HPSI Calculations (RAI-l153)

Should you have any questions on the contents of this progress report, do not hesitate to contact me at (610) 855-2366.

l Sincerely, l

Daniel L. Curry k l

Project Director DLC/cyb 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 l'

PPNU1217. Doc

r

\\

Attachment A to March 6,1998 Bi-weekly Report 1

Discrepancy Report Summary and Status i

449 Preliminanj DR Numbers issued by Parsons 4

i 326 Preliminary DRs approved of which 8 determined to be invalid 92 Responses received to date from NU 30 DRs CLOSED 57 DRs OPEN 05 DRs IN-PROGRESS (Awaiting revic,ed response from NU)

Of the 30 Valid and Closed Discrepancies resolutions 12 Confirmed Discrepancies 11 Previously Identified by NNECo 7 Non-discrepant Conditions Of the 12 Confirmed Discrepancies e

0 - Level 1 0 - Level 2 0 - Level 3 12 - Level 4 i

Attachment B: Tier-2 AMSR Validation Onen items (Status as of 3/09/98)

This attachment lists information needed to complete validation of the Critical Design Charactenstics 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-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.

UlR-288 RCS Pressure Uncertainty UIR-929 Pressurizer Level Revised FS AR Chapter 14 Analyses - 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-l115 31 Mar 98 RAI(later) 14.1.5 Main Steam Line Break (RCS Analysis) 127 Feb 98 Rt 31 Mar 98 RAI(later) 14.2.1 Loss of External Load L27 Feb 98 R3

' Complete-!

RAI-l128 14.2.4 Closure of Main Steam Isolation Valve f27 Feb 98 Rs Complet6 RAI-l128 14.2.7 Loss ofNormal Feedwater Flow 27 Feb'98'R$

31 Mar 98 RAI(later) 14.4.1 Startup Rod Withdrawal Accident RAI-l115 31 Mar 98 RAI(later) 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) 14.6.5.2 Small Break LOCA RAI-1115 30 Apr 98 RAI(later) 14.6.3 Steam Generator Tube Rupture RAI-l115 31 Mar 98 RAI(later) 14.8.2.1;.! Containment Analysis (MSLB)?

. Received 1 Interim 6 Mar 98 R1 (14.8.2.1) Containment High Pressure Trip During RAI-l115 31 Mar 98 RAI(later)

MSLB 14.8.2.2e.' Containment Analysis (LOCA)4 Received.

Complete:

6 Mar 98'Re RC Pump Coastdown Curve RAI-l115 31 Mar 98 RAI(later)

Note: R = Documents received by Parsons on indicated date Reauests for AdditionalInformation None

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