ML20249A302
| ML20249A302 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/10/1998 |
| From: | Curry D AFFILIATION NOT ASSIGNED |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUM2-PPNR-1580, NUDOCS 9806160285 | |
| Download: ML20249A302 (7) | |
Text
l
.1 " PARSONS Daniel L Curry, Vice President. Nucinar Servces Parsons Energy & Chemicals Group Inc 2675 Mo(gantown Road
- Reading, Pennsylvania 19607 * (610) 855-2366
- Fax: (610) 855-2602 June 10,1998 Docket No. 50-336 Parsons NUM2-PPNR-1580-L U.S. Nuclear Regulatory Commission Attention: Document Contrd Desk Washington, D.C. 20555 Millstone Nuclear Power Station Unit No. 2 Independent Corrective Action Verification Procram (ICAVP)
Gentlemen:
Pursuant to your recent request, attached please find the Millstone Unit 2 ICAVP Bi-Weekly Report for week ending June 5,1998.
Please call me at (610) 855-2366 if you have any questions.
Sincerely, Daniel L. Curry Parsons ICAVP Project Director
/
DLC:cyb Attachments 1.
Bi-Weekly Report f
cc:
E. Imbro (2)- USNRC R. Laudenat - NNECo J. Fougere - NNECo Rep. Terry Concannon - NEAC Project Files-9906160295 990610 4'
PDR ADOCK 05000336 P
,,,3-PAGEI Encompass g:
PPNR1580. doc
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PARSONS Daniel L Curry, vce Prwant, toc +ar sow es l
Parsons Energy & Chemicals Group Inc-l 2675 Morgantown Road + Rear.bng Pennsylvania 19607 * (610) 855-2366 Fax (610) 855-26o2 June 10,1998 Doc. ID: NUM2-PPNU-1579-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 i
Dear Mr. Laudenat:
The following represents a bi weekly progress report for work contpleted on Millstone Unit 2 ICAVP for the week ending June 5,1998.
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.
e AFW system review is moving forward with recent receipt of new system calculations.
l RRC system review in progress.
e EDG system review in progress.
l Programs associated with EQ, HELB, SB0 and Appendix R are on-hold pending receipt of updated e
information from NNECo.
Impact of delayed accident reanalysis on Tier 1 systems review is still to be determined.
Tier 2 - Accident Mitigation System Review Analysis Review - 29 Design Basis Events (DBEv):
e 12 DBEv Discovery Complete 3 DBEv Discovery Complete (Back check revised analysis when received) 3 DBEv Discovery Complete (Fuel handling accidents, previously reported as discovery complete, are being reanalyzed by NNECo) 9 DBEv Validations in Progress (Need 4 Revised Analyses) 2 DBEv Validations in Progress (Need Design inputs and Revised Analysis)
Design inputs have been received for 1) of the 16 DBEv being reanalyzed by NNECo. Completed e
analyses have been received for 4 of the 16 DBEv. Two additional analyses are reported as accepted by NNECo during this reporting period. These have been requested by Parsons (RAI-1699).
NNECo pravided a schedule update on June 2,1998. This status is shown in Appendix B. The schedule for completion of the 5 radiological events is being reevaluated by ' NECo.
N 1
b
l Mr. Richard Laudenat Northeast Nuclear Energy Company NUM2-PPNU-1579-L l
June 5,1998 l'
Discovery complete date is estimated as 4 weeks following receipt of revised analyses.
Tier 3 - Process Review I
Tier 3 review of change process samples is complete.
Five additional setpoint change requests are in review 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 the upgrades.
Other Activities:
Phone conferences completed on May 19,21,26 and 28,1998.
Discrepancy Reports See Attachment A for details RAI (Status)
A total of 1735 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) 355-2366.
Sincerely, Daniel L. Curry Project Director DLC/cyb Attachment I
cc:
J. Fougere E. Imbro(USNRC)
E. A. Blocher M. J. Akins J. L. Caldwell W. L. Dobson.
R. T. Glaviano J. F. Hilbish l
Project Records 1
l l
2 of 2 Encompass Letter PPNUl579. Doc
Attachment A to June 5,1998 Bi-weeldy Report Discrepancy Report Summary and Status 608 Preliminary DR Numbers issued by Parsons 488 Preliminary DRs approved of which 15 detennined to be invalid 132 Responses received to date from NU 37 DRs CLOSED 62 DRs OPEN 33 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
4 Attachment B: Tier-2 AMSR Validation Ocen items (Status as of 6/05/98)
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 Enci Bldg Ventilation System (NNECo response received. Parsons review in progress)
DR-033 HPSI Flow DR-045 -
Deboration During Startup 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 (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-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 Acci.ient Revised FSAR Chapter 14 Analyses - 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 revised analyses.
Evesy3pMjg'degg,'
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,,i g g~,Designputsj (NNEC6 Accept JevisedyR^,
g gtx
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- n FW A h6 Analysis'(ECDyn
? Analysis 959 s
14.1.3 Increase in Steam Flow 127EeF98 RM 15 Jun 98 RAI(later) 14.1.5 Main Steam Line Break (RCS Analysis) f27 fee 98K4:0 15 Jun 98 RAI(later) 11 4.2;1 " ' s LiisWExternalued e/c wu 27 M 98R 4 CaseteleWse* f23h98Rif 14.2.4 o ClosineWMain Steam isolation Valve ~ /% 27M98 RW-CanelateMs@W s23Maf98Rn 14.2.7 Loss of Normal Feedwater Flow 127M 98 RE 5 Jun 98 RAI(later) 14.4.1 Startup Rod Withdrawal Accident 124 Mar 98 RR C on elate
- W D W RAI-1699 j
14.4.6 CVCS Malfunction Causing RCS Deboration 128bir.98TR$ fWiMMib RAI-1699 14.6.5.1 Large Break LOCA (RCS Analysis) i28br'98 KW 31 Aug 98 RAI(later) 14.6.5.2 Small Break LOCA D28%pr98 RW 17 Jul 98 RAI(later) 14.6.3-Steam Generator Tube Rupture RAI-l115 12 Jun 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) 14,8.251tWh Anstras*(MSLB)n: 4*PA Received ma Complete AN ~, 16 Mae 98'RL (14.8.2.1) Containment High Press Trip During MSLB
?28 fair 98 Re 15 May 98 RAI(later) 14,4.21e f%8miama=* Analysis (LOCA)392 Ae' :Rabeived M ? CompleteW' ' - L6 Mar 98 Re 14.8.4 Radiological - Design Basis Accident RAI-1573 31 Jul 98 RAI(later)
RC Pump Coastdown Curve
!24 Mar 98 R%
1 May 98 RAI(later)
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