ML20151T304
| ML20151T304 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/31/1998 |
| From: | John Nakoski NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9809090342 | |
| Download: ML20151T304 (46) | |
Text
_ _ - ~ _ _
3
' August 31', 1998 j
- ' t.lCENSEE:
Northeist Nuciser En:rgy Comprny (NNECO)
FACILITY:
Millstone Nuclear Power Station, Unit 2
SUBJECT:
AUGUST 17,1998, MEETING REGARDING THE MILLSTONE UNIT 2
. INDEPENDENT CORRECTIVE ACTION VER FICATION PROGRAM On August 17,1998, the staff of the Special Projects Office (SPO) of the Office of Nuclear Reactor Regulation met with representatives of Northeast Nuclear Energy Compeny (NNECO) and Parsons Power Group, Inc. (Parsons) to discuss issues identified in the Unit 2 Independent Corrective Action Verification Program (ICAVP).
During the meeting, Parsons provided the current status of its efforts at implementing the
. ICAVP at Millstone Unit 2. Also discussed were the changes that are being implemented to the l
- lCAVP process at Unit 2 based on the lessons learned from the ICAVP conducted at Unit 3.
These changes had previously been discussed with the NRC SPO staff. Because Parsons is nearing completion of the discovery phase of the ICAVP, the changes are focused on reducing the scope of Parsons' review of corrective actions based on the NRC's determination that NNECO's corrective action program was satisfactory for restart of Unit 3.
I Another area discussed during the meeting was related to the issues raised in discrepancy report (DR)-0027 on a potential single-failure vulnerability of an Enclosure Building Ventilation l
System exhaust damper. The DR is being forwarded to the NRC for review and final resolution. provides a list of meeting attendees. Enclosure 2 provides the handout used by Parsons during the meeting that provides a summary of the changes to the ICAVP process and the status of its efforts. Enclosure 3 provides NNECO's handout used during discussions of
. DR-0027.
Originalsigned by John A. Nakoski, ICAVP Program Coordinator ICAVP Oversight Branch Office of Nuclear Reactor Regulation Docket No. 50-336 l
Enclosures:
As stated (3) cc w/encis:. See next page cD\\
f DISTRIBUTION:
l HARD COPY Docket File SPO reading "PUBLIC Elmbro JDurr RPerch ACRS PKoltay -
JLuehman PNarbut RMcIntyre OGC l
E-MAIL w/ encl ionly SCollins/FMiraglia
.WTravers - PMcKee WDean DMcDonald LBerry TMartin (SLM3) BMcCabe L
' DOCUMENT NAME: C:\\MYFILES\\lCAVP\\MEETSUM\\TRIPRPT.019 L
- See previous concurrence page.
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To receive a copy of tNs document truhcated in the bor "C's Copy without attach /enct "E" = Copy unth attach /enci"N" = No copy OFFICE ICAVP/ADT E
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ICAVP/ADT
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1 NAME-JANakoskiN
'LBerry* '
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I DATE 9 / 1 /d8' 8 / 24 /98 8 / 31'/ 98' 8 / 31 / 98 OFFICIAL RECORD COPY-a
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9809090342 990831 PDR ADOCK 05000336 i
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UNITED STATES
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l NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20M1
- s s s +,o August 31, 1998 LICENSEE:- Northeast Nuclear Energy Company (NNECO)
FACILITY:
Millstone Nuclear Power Station, Unit 2
SUBJECT:
AUGUST 17,1998, MEETING REGARDING THE MILLSTONE UNIT 2 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM l
On August 17,1998, the staff of the Special Projects Office (SPO) of the Office of Nuclear Reactor Regulation met with representatives of Northeast Nuclear Energy Company (NNECO) and Parsons Power Group, Inc. (Parsons) to discuss issues identified in the Unit 2 Independent Corrective Action Verification Program (ICAVP).
During the meeting, Parsons provided the current status of its efforts at implementing the ICAVP at Millstone Unit 2. Also discussed were the changes that are being implemented to the ICAVP process at Unit 2 based on the lessons teamed from the ICAVP conducted at Unit 3.
These changes had previously been discussed with the NRC SPO staff. Because Parsons is nearing completion of the discovery phase of the ICAVP, the changes are focused on reducing the scope of Parsons' review of corrective actions based on the NRC's determination that NNECO's corrective action program was satisfactory for restart of Unit 3.
i Another area discussed during the meeting was related to the issues raised in discrepancy report (DR)-0027 on a potential singie-failure vulnerability of an Enclosure Building Ventilation System exhaust damper. The DR is being forwarded to the NRC for review and final resolution. provides a list of meeting attendees. Enclosure 2 provides the handout used by Parsons during the meeting that provides a summary of the changes to the ICAVP process and the status of its efforts. Enclosure 3 provides NNECO's handout used during discussions of DR-0027.
h j
hn A. Nakoski, ICAVP Program Coordinator J AVP Oversight Branch Office of Nuclear Reactor Regulation Docket No. 50-336 l
Enclosures:
As stated (3) cc w/encls: See next page l
l
~ -.. -..
Millstone Nuclear Power Station Unit 2 cc:
Lillian M, Cuoco, Esquire Mr. F. C. Rothen Senior Nuclear Counsel Vice President -Work Services Northeast Utilities Service Company Northeast Utilities Service Company P. O. Box 270 P. O. Box 128 Hartford, CT 06141-0270 Waterford, CT 06385 Mr. John Buckingham Ernest C. Hadley, Esquire Department of Public Utility Control 1040 B Main Street Electric Unit P.O. Box 549 10 Liberty Square West Wareham, MA 02576 New Britain, CT 06051 Mr. John F. Streeter Mr. Kevin T. A. McCarthy, Director Recovery Officer - Nuclear Oversight Monitoring and Radiation Division Northeast Utilities Service Company Department of Environmental Protection P. O. Box 128 79 Elm Street Waterford, CT 06385 Hartford, CT 06106-5127 Mr. David B. Amerine Regional Administrator, Region i Vice President - Human Services U.S. Nuclear Regulatory Commission Northeast Utilities Service Company 475 Allendale Road P. O. Box 128 King of Prussia, PA 19406 Waterford, CT 06385 i
First Selectmen Mr. Allan Johanson, Assistant Director l
Towre of Waterford Office of Policy and Management Hall of Records Policy Development and Planning 200 Boston Post Road Division Waterford, CT 06385 450 Capitol Avenue - MS# 52ERN P. O. Box 341441 Mr. Wayne D. Lanning Hartford, CT 06134-1441 Deputy Director of Inspections Special Projects Office Mr. M. H. Brothers 475 Allendale Road Vice President - Operations King of Prussia, PA 19406-1415 Northeast Nuclear Energy Company P.O. Box 128 Charles Brinkman, Manager Waterford, CT 06385 Washington Nuclear Operations ABB Combustion Engineering Mr. J. A. Price 12300 Twinbrook Pkwy, Suite 330 Director - Unit 2 Rockville, MD 20852 Northeast Nuclear Energy Company P.O. Box 128 Senior Resident inspector Waterford, CT 06385 l
Millstone Nuclear Power Station l
clo U.S. Nuclear Regulatory Commission l
P.O. Box 513 Niantic, CT 06357 l
l
. - _ ~.
Millstone Nuclear Power _ Station Und 2 '
cc:
Mr. B. D. Kenyon (Acting)
Attorney Nicholas J. Scobbo, Jr.
Chief Nucler Officer-Millstone Ferriter, Scobbo, Caruso, Rodophele, PC Northeast Nuclear Energy Company 1 Beacon Street,11th Floor P.O. Box 128 Boston, MA 02108 Waterford, CT 06385 Mr. J. P. McElwain Citizens Regulatory Commission Recovery Officer-Millstone Unit 2 ATTN: Ms. Susan Perry Luxton Northeast Nuclear Energy Company 180 Great Neck Road P. O. Box 128 Waterford, CT 06385 Waterford, Connecticut 06385 Deborah Katz, President Mr. M. L. Bowling Citizens Awareness Network Recovery Officer - Technical Services P. O. Box 83 Northeast Nuclear Energy Company Shelbume Falls, MA 03170 P. O. Box 128 Waterford, CT 06385 The Honorable Terry Concannon Co-Chair Nuclear Energy Advisory Council Room 4035 Legislative Office Building Capitol Avenue Hartford, CT 06106 Mr. Evan W. Woolhicott Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070 Little Harbor Consultants, Inc.
Millstone -ITPOP Project Office P. O. Box 0630 Niantic, CT 06357-0630 Mr. Daniel L. Curry Project Director Parsons Power Group Inc.
2675 Morgantown Road Reading, PA 19607 l
1 LIST OF ATTENDEES
. Millstone Unit 2 -lCAVP Status August 17,1998 - 1:00 p.m.
NAME ORGANIZATION POSITION Eugene Imbro NRC Director ICAVP Oversight, NRR John Nakoski NRC ICAVP Program Coordinator, NRR Daniel G. Mcdonald NRC Senior Project Manager, Millstone Unit 2 Dan Curry Parsons Project Director Wayne Dobson Parsons Tier 3 Lead John Hilbish Parsons Regulatory Lead Ron Smith Parsons -
Tier 1 Lead (Acting)
Mike Akins Parsons Tier 1 Lead Trent Powers Parsons DR Coordinator Marty Bowling NU Recovery Officer, Millstone Unit 2 Richard Laudenat NU ICAVP Project Director Joe Fougere NU Manager, ICAVP
-1
-i t
MILLSTONE UNIT 2
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Parsons Power August 17,1998 Waterford, CT r
I w
l l
Agenda i
[
e Introduction / Objective t
i e Tier 1 Systems l'
I e Programs l
+ MOV i
+ Appendix R l
+EQ
+ SBO i
+ HELB j
l m3 L
PARSONS 08/17/98 2
I
l Agenda (continued) e Corrective Action Review e Discrepancy Reports f
e Tier 2 i
4:s: Tier 3
[
e DR-0027 i
4:s: Summary l
en f, PARSONS l
osiu m 3
[
Tier 1 - HPSI e Items to be Completed
- DR Response and Closeout
- Final System Report e Items Needed from XKECo
- Outstanding RAI's RAI-1697
)
'aj
'j
~
L PARSONS l
~l
e Tier 1 - AFW e Items to be Completed
- DR Preparation and Issue i
- DR Response and Closeout
- Final System Report e Items Needed from XKECo
- Outstanding RAI's RAI-1526 RAI-1540 RAI-157.1 RAI-1645 RAI-1687 RAI-1786 RAI-2093 RAI-0921 RAI-1087 RAI-1520 RAI-1726 RAI-2085 RAI-1890 RAI-2083
[
osnws 5
t I
Tier 1 - RRC e Items to be Completed
- DR Preparation and Issue l
- DR Response and Closeout
- Final System Report e Items Needed from NNECo
- Outstanding RAI's RAI-1125 RAI-l367 RAI-1517 RAI-1560 RAI-1641 RAI-1677 RAI-2004 RAI-2047 RAI-2048 RAI-2066 RAI-2094 E a==o==
l
Tier 1 - EDG e Items to be Completed
- DR Preparation and Issue
- DR Response and Closeout i
- Final System Report e Items Needed from XKECo
- Outstanding RAI's RAI-1223 RAI-1609 RAI-1613 RAI-1734 l
RAI-1773 RAI-1-794 RAI-1943 RAI-2035 RAI-2070 RAI-2028 j
i L
PARSONS
MOVProgram Review l
i Anuroach i
e Close existing DR's at existing levels as valid - no further review e Sample revised calculations for valves from MOVATS program (identified in DR-0248)
Items Needed from NNECo i
e RAI-2091 E =a=o==
1
_ - - -,. ~,,,, _ -,..
m.
-l Appendix R Review
\\
4 Approach e Appendix R review will focus on 2 fire
)
areas e Area 1 - Typical Appendix R electrical review based on safe shutdown analysis for Tier 1 components I
e Area 2 - Circuit based approach for Tier 1 components E2 I
PARSONS i
08/I7/98 9
j
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I i
Appendix R Review
\\
l Items Needed from NNECo e Revised Appendix R Compliance 1
Documentation e Applicable Abnormal Operating Procedures addressing Appendix R safe shutdown for j
selected fire areas i
e Documentation of manual actions
=>
ounm to PARSONS i
~
EQ Review s
Anoroach e Sample based on selected Tier 1 components l
e Components selected based on industry experience and maintenance history e Sample will include components qualified j
under DOR guidehnes I
Eh b
08/I7/98 11 l
EQ Review l
l Items Needed from XKECo e For selected components
- Test Report Assessments (TRAs)
- Environmental Qualification Reports (EQRs) l 1
08/17/9s 12
P I
SBO Review l
i i
Annroach e No further Parsons review - SBO is 3
included in NRC's SIL for review i
Items Needed from XKECo t
@ h_one r
i I
E PARSONS l
08/1788 13
HELB Review Approach s No further Parsons review s Close existing DR's Items Needed from XKECo e None i
E2 08/17S 8 I4 l
'i
o i
Corrective Action Review L
Anuroach
?
e From remaining CAs in Tier 1 scope l
- Remove NRC SIL items
- Concentrate on CAs completed or scheduled for F
completion in 1998
- Sample ~ 35 items 1
- Review Closure Packages for sample population j
i i
5 08/17/98 15
Corrective Action Review -Information Needed l
e SIL Items
- Which CR's, ACR's, UIR's are related to the SIL issues?
e Status and Schedule 1
- Which CR's, ACR's, UIR's were closed in 1998?
l
- What is the closure schedule for the open items?
e Closure Packages
- Parsons will issue RAI for sample of about 35 CR's, ACR's, j
UIR's closed in 1998
- Closure Package Prepared by NNECo should document the issue, the process followed and the outcome.
r U
PARSONS i
.4 I
1 NRC Requested Additional Tier 3 Items i
e Total Scope from 12/22/97 XRC letter
- 38 CR/ACR
- 26 UIR
- 11 EWR 1
- 11 FSARCR i
i e Current Status
- 19 Complete,11 In Process j
54 Need NNECo Closure Packages j
5 08/17MS 17 I
Tier 3 (NRC) Scope - NNECo Actions Needed Parsons has issued RAI-2096 to obtain closure packages for the following NRC Selected Tier 3 Scope Items:
UIR's CR/ACR's CR/ACR's EWR's 1083 7958 M2-97-0586 2-93-072 1442 11137 M2-97-0641 2-94-059 1584 M2-96-0240 M2-97-0841 2-94-186 1666 M2-96-0305 M2-97-0875 2-95-012 1804 M2-96-0455 M2-97-0898 2-95-016 1824 M2-96-0476 M2-97-0923 2-96-018 A& B 1910 M2-96-0569 M2-97-0984 2-96-142 2625 M2-96-0609 M2-97-1125 2-96-148 2796 M2-96-06i3 M2-97-1207 2-97-095 2880 M2-96-0666 M2-97-1212 2-97-116 2900 M2-97-0356 M2-97-1613 2-97-167 3026 M2-97-0359 M2-97-1791 3182 M2-97-0391 M2-97-1834 3292 M2-97-0412 M2-97-2060
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PARSONS
O r
DR Processing Enhancements
[
l e An individual has been assigned as a focal point for DR responses, expediting the resolution of l
Parsons concerns, and to act as an interface with XKECo during DR discussions.
i i
e Role is also to ensure that Parsons concerns are i
clearly communicated and understood.
j ARSONS osti7/os i9
Processing ofLevel3 DRs e DRs for which there is agreement that a DR is a Level 3, Parsons will classify the resolution as "Open Pending". NRC will select a sample ":o review final corrective actions. If acceptable, remaining Open Pending DRs will be closed.
e This approach is consistent with methods being used for Corrective Action closures.
1 U
08/17/98 20
n Processing ofLevel4 DRs i
e For Level 4 DRs accepted as valid, XVECo will provide the CR number for corrective actions that j
will be tracked and performed.
l e Parsons will close the DR based upon this information.
i 5'^5""5
.,m u
t
DR Status DR Preliminary Present Number Sign. Level Status Sign. Level 0027 1
Open - Follow-up 1
0113 1
Open - Follow-up 3
0119 2
Open - Follow-up 2
0127 1
Open - Pending 3
0312 1
Unresolved 0313 1
Open - Follow-up 3
i U
, 'I osiu m n
PARSONS
P I
Tier 2 - AMSR Review e Revised approach for remaining 7 Reanalyses
- Use existing design inputs to complete review of 5 analyses
+3 are complete - remaining 2 complete by 28 August 1
+ Continue review based on existing design inputs
+ Review reanalyses when complete
'j
=
PARSONS om m, u
i
f Tier 2 - AMSR Review i
I Information needed from XVECo j
e RAIs 1565 2051 (Will be revised to provide only 2 of 7 reanalysis) 2065 2097 l
i f
-en r
08/17M8 24
a Tier 2 - AMSR Review i
Information needed from XKECo 1
l e Closeout Packages supporting validation ACR-7910 AR-98008632 UIR-0170 UIR-0209 UIR-0213 UIR-0288 i
UIR-0929 UIR-1345 UIR-1415 f
UIR-2168 UIR-2510 UIR-2610 UIR-2603 UIR-2684 UIR-2757 UIR-2766 UIR-2816 UIR-2817 UIR-3013 UIR-3129 UIR-3198
[
e Additional Packages may be required as a result of validation i
J OR/17/98 25
Tier 3 - Process Review Summary i
e Remaining Tier 3 efforts
+ Vendor Manual upgrade review.
l l
>Limitorque Valve Motor Operators
> Centrifugal Pumps
> Reactor Trip Switchgear
>48015KVA Single Phase Inverters and Static Switches i
>480V MCCs
>AFW Pump Turbine
+ Information Needed.
>RAI 1803 - 480V MCCs Vendor Manual t
>RAI 1894 - AFW Pump Turbine Vendor Manual
>RAI 2086 - Maintenance procedure incorporation of Upgraded VTM information.
iiiis L
PARSONS 08/17N8 26
o
- 'i i
i i
NRC/ Parsons DR 0027 I
l Enclosure Building Design 9
h k
i
Overview, Mike Ahern l
l Five Issue DR Rated Significance Level 1 Issues Discussed in Detail in Previous Public Meetings with Parsons One Remaining Level 1 Issue; Enclosure Building Integrity following a single Failure of 2-AC-11 NU Concludes Millstone 2 Complies with License Bases, Public Health and Safety i
Assured
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Issue Description, Clark Maxson
)
i Millstone 2 Enclosure Building Ventilation Layout Scenario
- Infrequent Purge Operation, research of a sample year concluded Enclosure Building purge occurs less than 7% of the time i
I
- LOCA Coincident with Single Failure of 1-AC-11 to close
- Results in Main Exhaust Fans.and EBFS Fans Pulling on Enclosure Building i
FROM OUTSIDE AIR 1 r FROM SECONDARY RADWASTE
~
CONTAINMENT VENT ENCLOSURE SYSTEM AC-B J
(Z-1 )
TO UNIT 2 FROM STACK Q UEL HANDLING 0
S 2-HV-299 SYSTEM (A,B,C,)
PLENUM C-fZ-){
2-AC-22 F-34A F-348)
CLOSES OPENS -
(F-34C )
ON CIAS ON CIAS
~
STA MAIN f.
t EXHAUST CONTAINMENT
. 2-EB-54 FANS PU GE FROM 3
H OUTSIDE UNIT AC-1 w
(Z-1 )
F-23 AC-130 2-EB-43 (EBFS FANS) f I
CLOSES (Z-2 )
8
~
ON CIAS STOPS 7
A 7 A 6 ON CIAS h
q' F-25B AC-5 AC-4 LC LC EBFS FANS START ON EBFAS EBFS AND CONTAINMENT & ENCLOSURE BUILDING PURGE SYSTEM e
SKM-MCR-E8FS.dgn
.t t
License Bases L.ack of single failure isolation for 2-AC-11 was addressed at the time of Plant License and later reaffirmed Post Startup in 1995 j
. Both times concluded 2-AC-11 does not need to be Single Failure Proof based on acceptable consequences
License Bases, Original 1973-1974 XRC/NU Question and Answers NRC Question "... demonstrate flow in purge lines will be inward following a LOCA including failure of AC-1 or AC-11"
License Bases, Original (cont.)
}
XS~ECO Response-Evaluation of bounding AC-1 I
failure determined that with 2 EBFS fans running, l
that flow would still be into the Enclosure Building l
1 NRC SER for Millstone 2 dated May 10,1974-
" Based on our review of the proposed design and l
predicted performance-of the EBFS, we have j
concluded that the system meets the intent of GDC 41,42,43, and 64
License Bases, Post Startup j
1995 Engineering Analysis in support of LER 94-040-02:
- Postulating a single failure of 2-AC-11 during j
purging is beyond the License Bases 1
- Negligible Public Safety Impact based on the l
probability of occurrence and consec uences l
License Bases, Post Startup (cont.)
- Instrumentation would alert operators to the poteiltial release and terminate it by shutting off the main exhaust fans
- Thus, the plant is adequately and safely designed to mitigate the consequences of a LOCA
- No modifications are required to eliminate the 2-AC-11 single failure
License Bases, Post Startup (cont.)
- NRC reviewed LER 94-040-02 and the NRC Safety Evaluation concluded:
The fact that the vulnerability exists only during purging of the Enclosure Building reduces the probability by at least an order of magnitude", and 4
License Ba.ses, Post Startup (cont.)
The fact that the potential release path is monitored for radioactivity provides a high degree of confidence that manual action would be quickly taken to terminate the release by shutting off the main ventilation fans"
License Bases, Post Startup (cont.)
I Based on these considerations, the staff
)
accepts the licensee's position that the I
correction of the AC-11 single failure vulnerability is unnecessary. It is also noted that the licensee has performed an Integrated Safety Assessment Program cost benefit analysis...and determined that the potential safety benefit is insignificant."
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Beyond License Bases, "What If"
- Instrumentation would alert operators to the potential release and terminate it by shutting off the main exhaust fans Enclosure Building will not be significantly impacted
-Enclosure Building is designed and model tested to greater than 8 in. w.g.
-Maximum possible Enclosure Building negative pressure is 6 in. w.g.
l Beyond License Bases, "What If" (cont.)
Low probability event, purge operation is infrequent Conclusion, Public Health and Safety is Assured
o y
1 Conclusions, Mike Ahern i
Millstone 2 Complies with License Bases i
Significant Design Margin Covers "What If" Public Health and Safety Assured l
-.