ML20249C357

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Forwards Millstone Unit 2 Independent C/A Verification Program Bi-Weekly Rept for Week Ending 980619,per Request
ML20249C357
Person / Time
Site: Millstone Dominion icon.png
Issue date: 06/22/1998
From: Curry D
External (Affiliation Not Assigned)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUM2-PPNR-1625, NUDOCS 9806290109
Download: ML20249C357 (7)
v • d • e


Text

____-_- - __ - ___ - _ _ _ _ _ - _ _ - - - _

PARSONS Daniel L. Curry, Vice PresKnint Nuclear Services Parsons Energy & Chemoais Group Irc 2075 Morgantown Road + Reading, Pennsylvania '4607 + (610) QS-2366 + Fax: (610) 855. ?602

)

June 22,1998 Docket No. 50-336 Parsons NUM2-PPNR-1625-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) i Gentlemen:

Pursuant to your recent request, attached please find the Millstone Unit 2 ICAVP Bi-Weekly Report for

- week ending June 19,1998.

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

l Sincerely, i

)

dtt<

i Daniel L. Curry i

Parsons ICAVP Project Director DLC:cvb i

. Attachments.

1.

Bi-Weekly Report ec:.

E. Imbro (2)- USNRC R. Laudenat - NNECo -

'J. Fougere - NNECo Rep. Terry Concannon - NEAC i

' Project Files 1

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9806290109 980622

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ADOCK 050003362[

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PAGEI Encompass g'

PPNR1625. doc

d PARSONS i

Daniel L. Curry, vice President, Nuclear Sorvices Parsons Energy & Chernicals Group inc.

2675 Morgantown Road

  • Fax: (610) 855-2602 l

l June 22,1998 Doc. ID; NUM2-PPNU-1624-L Mr. Richard Laudenat Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 2 l

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 June 19,1998.

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 HPSI system discovery complete. Corrective Action Review and DR closeout is ongoing.

' AFW, RRC and EDG system reviews are target for discovery complete by July 31,1998. Target i

e discovery complete does not include Corrective Action Review, DR Closeout, Program Review (EQ, HELB, SBO and Appendix R) and impact of delayed accident analysis.

Programs associated with EQ, HELB, SBO and Appendix R are on-hold pending receipt of updated information from NNECo.

I Impact of delayed accident reanalysis on Tier 1 systems review is being tracked via system review e

checklist punchlist items for CDCs.

Tier 2- Accident' Mitigation System Review Analysis Review - 29 Design Basis Events (DBEv):

e-13 DBEv Discovery Complete i

6 DBEv Discovery Complete (Back check revised design inputs / analyses when received) 9 DBEv Validations in Progress (Need 5 Revised Analyses) 1DBEv Validations in Progress (Need Design Inputs and Revised Analysis for SGTR)

Revised Design Inputs are required for 3 radiological analyses (RAl-1573, RAl-1769),

e Completed analyses have been received for 6 'of the 16 DBEv. Four additional analyses are reported as e

accepted by NNECo. These have been requested by Parsons (RAI-1769).

NNECo provided a schedule update on June 12,1998. This status is shown in Appendix B.

Discovery complete date is estirnated as 3 weeks following receipt of revised analyses.

![

4 p-

' Mr. Richard Laudenat Northeast Nuclear Energy Company NUM2-PPNU-1624-L June 22,1998 Tier 3 - Process Review

~ Tier 3 review of change process samples is complete.

Review of five additional setpoint change requests were completed since the last progress report. This

' review was due to the identification of 74 additional SCRs in the sample population.

Review of Vendor Manual upgrade corrective actions has begun and will progress as NNECo completes s

  • the upgrades. Currently we are evaluating if the review sample can be selected from upgraded nunual i

- completed to date.

j.

- Other Activities:

Phone conferences completed on June 9,11,16 and 18,1998.

Discrepancy Reports _

See Attachment A for details RAI (Status)

A total of 1778 RAI's have been issued. Details of outstanding RAI responses and partial responses are

- provided on Attachment C.

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

i Sincerely, l

aniel L. Curry L

Project Director DLC/cyb Attachment-l L

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 i-2 of 2 Encompass Letter PPNU1624. Doc L

_ _ =

i

' Attachment A to June 19,1998 Bi-weekly Report Discrepancy Report Summary and Status 636 Preliminary DR Numbers issued by Parsons 497 Preliminary DRs approved of which 16 determined to be invalid 161 Responses received to date from NU 38 DRs CLOSED 73 DRs OPEN 50 DRs IN-PROGRESS (Awaiting revised response from NU on 2 DR's)

Of the 38 Valid and Closed Discrepancies resolutions 16 Confirmed Discrepancies 12 Previously Identified by NNECo 10 Non-discrepant Conditions Of the 16 Confirmed Discrepancies 0 - Level 1 0 - Level 2 0 - Level 3 16 ' Level 4

e

' Attachment B: Tier-2 AMSR Validation Open items

, (Status as of 6/19/98)

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 '

Enct Bldg Ventilation System (NNECo response received. Parsons review in progress)

~ DR-033 HPSI Flow DR-045 Deboration During Startup (NNECo response received. Parsons review in progress)

Rev i DR-202 MSSV Accumulation (NNECo response received. Parsons review in progress)

DR-205 Pressurizer Safety Valve Accumulation

. DR-313 RPS RC Low Flow Trip Setpoint (Parsons review of NNECo response complete.

Rev L

DR reclassified by Parsons from Level I to Level 3).

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.

l:

..UIR-288. RCS Pressure Uncertainty UlR-929, Pressurizer Level UlR-2601 Containment Purge Flow Rate Used In Fuel Handling Accident Analysis UlR-3198 Containment Purge Isolation Time Assumed for Fuel Handling Accident E

Revised FSAR Chapter 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 L

revised analyses.

Evati

.~

, #8 e

^

W "gn inputsn <NNECo' Accept.

Revised Ee Desi 4ssds'ca~

a

~"iW AnalWis(ECDDi %isisiisW[

L 14.1.3 Increase in Steam Flow f27,Feb 98 R4 Complete'##n RAI-1769 L

14.1.5 Main Steam Line Break (RCS Analysis) 127 Feb98 Ru CompleepWM V RAI-1769 1411n: J4ceseflhdarealGiiulMM iw hW2M n 427eFeb98: Rex Camelstensk8 WMiliME 1414 ^ s ClosureofMain"Stemin'isolsexwtValveli

  • s27 Feb 98 R$s Complete WM MMiMBE L

14.2.7 Loss of Normal Feedwater Flow 42~7 Feb 98 R$

Comple46E2h RAl-1769

('

il4MW $tastus Rod,Wnhdrawai'AscidentMin + A 124: Mar 98!RW Ccealese@he st91mii98R$

l(4.6M 4CVCS Malfhnctiosi Causina RCS Deboration F281 Ann'98 RW Complete e M191miiMX#

L 14.6.5.1 Large Break LOCA (RCS Analysis)

!28 Ass 98Rie 31 Aug 98 RAI(later) 14.6.5.2 Small Break LOCA-128%pih98b 17 Jul 98 RAI(later)

J 14.6.3 <

Steam Gen Tube Rupture - Mass Release

$1/A$gggfid Mynpigted;dM RAl-1769 L

Steam Gen Tube Rupture - Radiological Calc RAI-1769 31 Jul 98 RAI(later) 14.7.4.2.1-Fuel Handling Accident in Spent Fuel Pool RAI-1573 31 Jul 98 RAI(later) 14.7.4.2.2 Fuel Handling Accident in Containment 121on'98 RW 31 Jul 98 -

RAI(later) 14.7.5 Spent Fuel Cask Drop RAl-1573 31 Jul 98 RAI(later) 11814WContenment Analysis (MSL8)! "" / : 4" ReceivodiN e Complete - Ma T Maf98 M -

(14.8.2.1) Containment High Press Trip During MSLB

'28!Apr98 RW 15 May 98 RAI (later)

itA11&Tomaisnem Analyins(LOCA) M Received *WW Completeness @f 4Mn98WW 14.8.4 Radiological - Design Basis Accident -

112 M 98 RM 31 Jul 98 RAI(later)

RC Pump Coastdown Curve 024 Mn98 Rei 1 May 98 RAI(later)

Note: R = Documents received by Parsons on indicated date

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8 1

2 9 0 4 8 0 1 3 5 7 9 2 5 7 0 1 2 6 7 9 0 1

2 5 5 8 9 2 3 5 5 2 4 8 9 1

3 1

5 1

2 2 2 3 3 3 4 4 4 4 4 4 5 5 5 6 6 6 6 6 6 7 7 7 7 l 2

NA I

1 l

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 t

a 5 5 5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 t

ET o

1 PA AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA u l I I

l l

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l I

l l

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I I

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I l

I I

I l I I

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b OD RRRRR RRR R RR RRR R RRRR RR RR RRRRRRRR RRRRRR R R R R_S

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