ML20248B993

Forwards Millstone Unit 2 Independent Corrective Action Verification Program bi-weekly Rept for Wk Ending 980515

ML20248B993
Person / Time
Site:	Millstone
Issue date:	05/22/1998
From:	Curry D AFFILIATION NOT ASSIGNED
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9806020036
Download: ML20248B993 (6)

Text

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r PARSONS Daniel L. Curry, Vee President. Nuclear Serwces Parsons Energy & Chemicals Group Inc.

267S Morgantowr1 Road a Reading. Pennsylvania 19607 * (610) 855-2366

• Fax: (610) 855 2602 l

l I

May 22,1998 l

Docket No. 50-336 Parsons NUM2-PPNR-1509-L j

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 Procram UCAVP)

Gentlemen:

Pursuant to your recent request, attached please find the Millstone Unit 2 ICAVP Bi-Weekly Report for week ending May 15,1998.

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

Sincerely, 4

Daniel L. Curry Parsons ICAVP Project D rector DLC:cvb Attachments 1.

Bi Weekly Report I

cc:

E. Imbro (2)- USNRC R. Laudenat - NNECo J. Fougere - NNECo Rep. Terry Concannon - NEAC Project Files

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j PAGEI Encompass g

PPNR1509. doc a

PARSONS Daniel L Curry, vice P<esoint tocser suce,

Parsons Energy & Cnem eats Group loc.

2675 Me;rgantown Road

• Reading. Pennsylvania 19607 + (610) 855-2366 + Fax: (610) 855-2602 May 22,1998 Doc. lD: NUM2-PPNU-1508-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 15,1998.

Project Schedule: I have deleted the forecast.Gr the discovery completion dates for Tier 1 activities. We are currently reevaluating the continuing schedule impact based upon the limited receipt ofinformation on Unit 2.

This reevaluation will include both the overall Unit 2 schedule and lessons teamed from Unit 2 ICAVP to da Tier 1 - System Vertical Slice Reviews HPSI system discovery complete. Corrective Action Review and DR closeout is ongoing.

AFW system review is moving forward with recent receipt of new system calculations.

RRC system review in progress.

EDG system review in progress.

Programs associated with EQ, HELB, SB0 and Appendix R are on-hold pending receipt of updated information from NNECo.

Impact of delayed accident reanalysis on Tier 1 systems review is still to be determined.

Tier 2 - Accident Mitigation System Review NNECo, NRC and Parsons met on May 12th to discuss Tier-2 status. NNECo identified 4 additional accident reanalyses being performed, along with estimated completion dates for each reanalysis. See Appendix B for revised dates. The following accident reanalyses were added:

Event 14.7.4.2.1 Fuel Handling Accident in Spent Fuel Pool Event 14.7.4.2.2 Fuel Handling Accident in Containment Event 14.7.5 Spent Fuel Cask Drop Event 14.8.4 Radiological-Design Basis Accident (3 Analyses)

Design inputs have been received for 1I of the 16 DBEv being reanalyzed by NNECo. Remaining design inputs are scheduled to be provided to Parsons by May 22nd.

. The short term staffing reduction identified in previous Bi-Weekly Progress Reports has been lifted, with recommencement of the RC Pressure Boundary Events (4) validation.

P

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I 1

.4 Mr. Richard Laudenat Northeast Nuclear Energy Company NUM2-PPNU-1508-L l

May 22,1998 Analysis Review - 29 Design Basis Events (DBEv) 11 DBEv Discovery Complete 3 DBEv Discovery Complete (Back check revised analysis when received) 2 DBEv Discovery Complete (Fuel handling accidents, previously reported as discovery complete, identified on May 12 as being reanalyzed) 10 DBEv Validations in Progress (Need 4 Revised Analysis) 3 DBEv Validations in Progress (Need Design inputs and Revised Analysis)

Discovery complete date is estimated as 28 August. To achieve this timing, revised design inputs are required by 21 May, and remaining reanalyses need to be sequenced and accepted as identified in the current NNECo schedule.

Tier 3 - Process Review NRC inspection ofICAVP Tier 3 completed on May 8,1998. The inspection found no significant

]

e deficiencies in Parsons Tier 3 scope of work.

Five additional setpoint change requests are in review due to the identification of 74 additional SCRs in the sample population.

An initial sample of updated vendor manuals has been selected for review based on the population of seven manuals completed to date. A schedule for the reviews is in preparation based on NNECo schedule to complete the manual updates in August.

Other Activities:

Phone conferences completed on May 5,7,12 and 14,1998.

Discrepancy Reports See Attachment A for details RAI (Status)

Total issued 1630 e

33 greater than 2 weeks / total outstanding 112 e

l HPSI -(RAI-0921, RAI-1054(p))

AFW -(RAl-1087)

RRC -(RAI-l125(p))

e EDG - (RAI-1223, RAI-1293, RAI-1618, RAI-1604)

Tier 2 Validation (RAI-l115(p), RAI-1314(p), RAI-1573) e Tier 3 (RAI-1591) e l

2 of 3 Eneompass Letter PPNU1508. Doc

b Mr. Richard Laudenat Northeast Nuclear Energy Company NUM2-PPNU-1508-L May 22,1998 Should you have any questions on the contents of this progress report, do not hesitate to contact me at.

(610) 855-2366.

Sincerely, M

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 3 of 3 Encompass Letter PPNU1508. Doc

1 Attachment A to May 15,1998 Bi-weeldy Report Discrepancy Report Summary and Status 577 Preliminary DR Numbers issued by Parsons 466 Preliminary DRs approved of which 15 determined to be invalid 122 Responses received to date from NU 37 DRs CLOSED 57 DRs OPEN 22 DRs IN-PROGRESS (Awaiting revised response from NU on 2 DR's)

Of the 37 Valid and Closed Discrepancies resolutions 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 j

i l

I L_______.__________________._____________________________._._______.__

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Attachment B: Tier-2 AMSR Validation Open items (Status as of 5/21/98)

This attachment lists information needed to complete validation of the Critical Design Characteristics associated with the FSAR Chapter 14 Accident Analyses.

Preliminary Discrepancy Reno,_ru - Provide completion schedule and closure package for the listed DRs.

DR-027 Encl Bldg Ventilation System (NNECo response received. Parsons review *n progress)

Rev DR-033 HPSI Flow DR-045 Deboration During Startup DR-202 MSSV Accumulation (NNECo response received. Parsons review in progress)

Rev DR-205 Pressurizer Safety Valve Accumulation

- DR-313 RPS RC Low Flow Trip Setpoint (NNECo response received. Parsons review in progress)

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 n29 - 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 Chaoter 14 Analyses - The below table lists events being reanalyzed by NNECo and identifies information needs to complete the Tier-2 validation. RAIs will be submitted upon hWECo acceptance of the '

revised analyses.

Event MgW J.y:

7<,7

Design Inputs - NNECoAccept MRevised MM(

2W W,$4 M en S-7

' // c 't ' '*-

Analysis (ECD)Si 7o s 14.1.3 Increase in Steam Flow

%[@!WiWRS 15 Jun 98 RAI(later) 14.1.5 Main Steam Line Break (RCS Analysis)

@fPi @$1RS$

15 Jun 98 RAI(later) 4G@lf%&libilNifBNReptidIMifWisin9himiill#4ffalNa M EW 082 !Camistelismf@aW 41559Hl5 iM2MECkesiisdrMdEStdifffsaladNWdWPBEW2% UK t2 iceinpfe# WG M

• 4HIERRW 14.2.7 Loss of Normal Feedwater Flow A VihlE$1M 29 May 98 RAI(later) 14.4.1 Startup Rod Withdrawal Accident s Gilient @ 25 May 98 RAI(later) 14.4.6 CVCS Malfunction Causing RCS Deboration d l M i W 22 May 98 RAI(later) 14.6.5.1 Large Break LOCA (RCS Analysis) p l 3Ei E! SR 15 Jun 98 RAI(later) 14.6.5.2- - Small Break LOCA iM fMilE E M 15 Jun 98 RAI(later) 14.6.3 Steam Generator Tube Rupture RAI-l115 29 May 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 RAI-1573 -

31 Jul 98 RAI(later) 14.7.5 Spent Fuel Cask Drop RAI-1573 31 Jul 98 RAI(later) 14A.3.W' Coenaiement AnalysittMSL8)$WW82WM RocchedW& CompleseWMeti 6MiF98Ke (14.8.2.1) Containment High Press Trip During MSLB 128?Ap(98 RW 15 May 98 RAI(later)

!!4.8120tontamment Analysis (LOCA)MeMe@$ RecchedMes th *Wer 4Mai98R$

I4.8.4 Radiological-Design Basis Accident RAI-1573 31 Jul 98 RAI(later)

RC Pump Coastdown Curve i24MaE98R%

1 May 98 RAI(later)

Note: R = Documents received by Parsons on indicated date