ML20216J056
| ML20216J056 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/12/1997 |
| From: | Reynolds S NRC (Affiliation Not Assigned) |
| To: | Schopfer D SARGENT & LUNDY, INC. |
| References | |
| NUDOCS 9709170144 | |
| Download: ML20216J056 (7) | |
Text
_
l Mr. Don Schopfer September 12, 1997 Verification Team Manager l
Sargent & Lundy 55 E. Monroe Street Chicago,IL 60603
Dear Mr. Sct.opfer:
The staff of the Special Projects Office of the Office of Nuclear Reactor Regulation has perused the various lists of items needing corrective action that have been identified by Northeast Utilities (NU) and have selected a number of these items for review by Sargent & Lundy (S&L) as part of Tier 3 of your independent Corrective Action Verification Program activities Millstone Unit 3. The enclosed list contains Licensee Event Reports, Adverse Condition Reports, and Condition Reports, Open item Reports, Unresolved item Reports, Final Safety Analysis Change Requests, and engineering evaluations and calculations; all of which are to be reviewed by S&L to determine that the corrective action taken by NU is adequate and in accordance with the licensirg and design basis, if you have any questions, please contact me at (301) 415-1332.
Sincerely, c, -
StMbey oNs, hief ICAVP Oversight Branch Special Projects Office Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See next page Distribution:
i Docket Flies (Docket 50-423)
PUBLIC?
WTravers JAndersen HEichenholtz AGody SPO R/F PMcKee WLanning PKoltay JLuehman DOCUMENT NAME:G:\\Reynolds\\ Tier 3S&L.cas TS receive a copy of this document. Indicate in the box "C" copy w/o attach /enci"E" copy wlattachtenci "N" no copy OFFICE C:lCAVP E
DD:lCAVP NAME SReynolds/srA Elmbro k DATE 9/h/97 -
9/1497 O'4 OFFICIAL RECORD COPY
,.~
i 970917
?" ^0144 97o912*#s!
lilRlEHJHIElllER
Northeast Nuclear Energy Company
- Millstone Nuclear Power Station Unit 3 cc:
Lillian M. Cuoco, Esquire Mr. William D. Meinert Senior Nuclear Counsel Nuclear Engineer Northeast Utilities Service Company Massachusetts Municipal Wholesale P. O. Box 270 Electric Company Hartford, CT 06141-0270 P. O. Box 426 Ludlow, MA 01056 Mr. Kevin T. A. McCarthy, Director Monitoring and Radiation Division Joseph R. Egan, Esquire Department of Environmental Protection Egan & Associates, P.C.
79 Elm Street 2300 N Street, NW Hartford, CT 06106 5127 Washington, D.C. 20037 Regional Administrator, Region l Mr. F. C. Rothen U.S. Nuclear Regulatory Commission Vice President - Nuclear Work Services 475 Allendale Road Northeast Nuclear Energy Company King of Prussia, PA 19406 P. O. Box 128 Waterford, CT 06385 First Selectmen Town of Waterford Emest C. Hadley, Esquire Hall of Records 1040 B Main Street 200 Boston Post Road P. O. Box 549 Waterford, CT 06385 West Wareham, MA 02576 Mr. Wayne D. Lanning Mr. John Buckingham Deputy Director of Inspections Department of Public Utility Control Special Projects Office Electric Unit 475 Allendale Road 10 Liberty Square King of Prussia, PA 19406-1415 New Britain, CT 06051 Michael H. Brothers Mr. James S. Robinson Vice President - Millstone Unit 3 Manager, Nuclear investments and Northeast Nuclear Energy Company Administration P. O. Box 128 New England Power Company Waterford, CT 06385 25 Research Drive Westborough, MA 01582 Mr. M. R. Scully, Executive Director Connecticut Municipal Electric Mr. D. M. Goebel Energy Cooperative Vice President - Nuclear Oversight 30 Stott Avenue Northeast Nuclear Energy Company Norwich, CT 06360 P. O. Box 128 Waterford, CT 06385 Mr. David Amerine Recovery Officer - Nuclear Engineering i
and Support i
(
Northeast Nuclear Energy Company P. O. Box 128 l
Waterford, Connecticut 06385 l
i f
_ _ - _ _.~ _
- Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 3 cc:
Deborah Katz, President Mr. B. D. Kenyon Citizens Awareness Network President and Chief Executive Officer P. O. Box 83 -
Northeast Nuclear Energy Company Shelbume Falls, MA 03170 P. O. Box 128 Waterford, CT 06385 Senior Resident inspector Millstone Nuclear Power Station Mr. Daniel L. Curry clo U.S. Nuclear Regulatory Project Director Commission Parsons Power Group Inc.
P. O. Box 513 2675 Morgantown Road Niantic, CT 06357 Reading, Pennsylvania 19607 Mr. Allan Johanson, Assistant Director Mr. Don Schopfer Office of Policy and Management Verification Team Manager Policy Development and Planning Division Sargent & Lundy 450 Capitol Avenue - MS# 52ERN 55 E. Monroe Street P. O. Box 341441 Chicago, Illinois 60603 Hartford, CT 061341441 Citizens Re0ulatory Commission ATTN; Ms. Susan Perry Luxton 180 Great Neck Road Waterford, Connecticut 06385
~
The Honorable Terry Concannon Co-Chair Nuclear Energy Advisory Council Room 4035 Legiciative Office Building Capitol Avenue Hartford, Connecticut 06106 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, Connecticut 06070 Little Harbor Consultants, Inc.
Millstone - ITPOP Project Office P. O. Box 0630 Niantic, Connecticut 06357-0630
MILLSTONE UNIT 3 1CAVP TIEfL3_CDERECTIVE ACT1QNJIEMS LicenseeluntReporta 1.
LER 06-44 AFW System Not rated for Containment Design Temperature 2.
LER 96 46 Containmant Purge Dilution Time Greater Than in FSAR 3.
LER 96 50 Chill Water Pump Suction Gages Don't Meet Section XV 4
Requirement 4.
LER 97-13 Fallure to Meet GDC57 for MSS Containment isolation Valve to the Aux FW Pump Turbine 5.
LER 97-16 Piping Supports for RHR Inconsistent with Design Details (Related to LER 96-07) 6.
LER 97-20 Elevated Containment Temperature Due to Reduced Cooling Capability 7.
LER 97-29 Design Basis Concern on SGTR Analysis for MSPRBV 8.
LER 97-30 Non Conservatism in the Low Temperature Overpressure Protection and Pressure / Temperature Limit Curves in the TS 9.
LER 97-31 RHR Valve Low Pressure Open Permissive Bistable Setting Set Non Conservatively 10.
LER 97-32 Calibration of Pumped Capacity Monitoring System Timers Not in Accordance with 18 Month Surveillance Requirement of the Tss 11.
LER 97-33 P-6 Bistable Reset Function Set Non Conservatively Resulting in TS Violation 12.
LER 97-34 Valves Not included in Containment isolation Valve Surveillance 13.
LER 97-36 Pipe Break Exclusion Zones Differ From Those Described within the FSAR 14.
LER 97-38 Single Failure Potential for Fuel Building Filter Exhaust Fans 15.
LER 97-39 Inoperability of Turbine Building Sump Effluent Monitor DAS-RES0 Due to a Failure to Recognize a Design Deficiency that Resulted in a TS Violation 16.
LER 97-43 Inadequate TS Surveillance for the ESFAS and Reactor Trip System Instrumentation Interlocks 17.
LER 97-45 Reactor Trip System Response Time Testing Not in Verbatim Compliance with TSs ACRn.AND_CEa 1.
CR M3-97-2090 Potentially Unanalyzed Condition involving RHR Temperature Transient and Cannot Find a Design Basis for Recirculating the RHS to the RWST Prior to Cooldown ENCLOSURE
\\
2.
CR M3-97-1863 RPS/ESFAS Setpoints are Based on Calc Methods and Assumption that are No Longer Appropriate -affects TSs -
3.-
CRs M3 97-2251 CRs Related to Parts Use (Material & Procurement, M3 97-2252 quality /none quality, and traceability)
M3-97_-2253 M3-97-2255-4.
ACR 00161*
Logic Diagram Not consistent With Design For FANS HVQ*FN5A,B,6A,8 - Potential IEEE 279 Noncompliance 5.
- ACR 01162*
EEQ Level Switches Not Replaced Prior to End of Life 10 Yr. EEQ Life Exceeded 3CCP*L5196A&B 6.
ACR : 03674*
Containment Liner Accident Temp May increase Higher than g
Originally Calculated 7.
ACR 05029*
Spent Fuel Pool Issues with Potential Regulatory impact 8.
ACR 06323*
Containment Base Mat Loading Assumed Apparently Less Than Peak bearing Pressure 9.
ACR 08411*
Nonconforming Material Installed without a Bypass-Jumper or Other Design Change 10.
ACR 10817' GL 91-15 Solenoid Valve Misapplication Review; MP3 Missed CNMT. Isolation Function i
11 ACR 13783*
Ma'ntenance Procedure for RX Trip Bkr Switch Gear Potentially inadequate (URI No.148 & 195)
- 12.
ACR M3-96-0081* Potential Electrical Separation Violations with Solid State Protection system (URI No. 388)-
l 13.
_ ACR M3 96-0233' Battery Room Temperature Questioned (URI No. 333) 14.
. ACR M3-96-0373* Question on 3 MSS *AOV31 A,B,D Component Replacement 15.
ACR M3-96-0933* SOV's, Target Rocks Will Open in The Reverse Direction due to Delta P 16.
CR M3-97-0167*
Plant Drawings Not in Accordance With Design 17.
CR M3-97 0429*
Cable Separation Violation Per spec 076 DWG EE-35-A 18.
CR M3-97-1273*
SEW Computer Calc for Rad Levels on EQ in ESE not Retrievable 19.
CR M3 97-1649*
Documents referenced in MP3740DA Are Not Retrievable From Documents-20.
CR M3-97-1664*
Dampers 3HVC*DMPF 07 and DMPF 08 Required to be QA CAT 1 Not Just FPQA
- ltems are considered closed by NU Q188 -
l 1.-
OIR 84 Containment Pressures: DBA Maximum & ESF Setpoints
2.
OIR 389 AOP 3573 Radiation Monitor Alarm Response Procedure for High Area Radiation Alarms RMS08-1 and RMS361 Not Consistent with o
FSAR 3.
OIR 101 There is No Means of Heating or Cooling the Pipe Tunnel Area (ESF Bldg)
OIR 102 Review Pipe Tunnel Area for Need of Having Cooling and/or Heating Requirements. If Necessary Make Required Modifications or Proceduralize Appropriate Compensatory Ventilation Actions 4.
OIR 482 Circulating & Service Water Ventilation System Class 1E Equipment Classificatcn 5.
OIR 391 inconsistent AFW Flowrate 6.
OIR 48 Lack of Procedural Guidance for Cross-ty.ag RPCCW to the CAR Coolers and NST Coolers 7.
OIR 131 Class 15 Battery Charger Regulation IRRs NOTES:
1.
All listed items are indicated to be in a closed status by NU 2.
UIRs selected do not have a corresponding ACR/CR No.
1.
UIR 156 Pipe Support Under RCS*V985 Questionable 2.
UlR 723 Installation of Unauthorized Hook Vents 3.
UIR 706 Pipe supports inside containment have SWEC QC Reject Tag 4.
UlR 408 Electrical /l&C Conduits Inside Contalment are Underwater and Corroded S.
UlR 134 Discrepancy on RHS Relief Valve Setpoint 6.
UlR 27 Pipe Installed Via AWO 7.
UIR 36 PDCR MP3-89-013 Containment Design pressure 8.
UlR 498 Does Not Reflect AFW Functions for Small Break LOCA Analysis' 9.
UIR 600 Setpoints Changed without SCR or PDCR 10.
UIR 443 Parts from Non-OA MCCs Labeled Non-QA Used in QA MCCs 11.
UlR 129 Circuit Breakers Were improperly Sized 12, UlR 113 Calculation Does Not Account for Parallel Charge Ops.
13.
UIR 158 RX Trip Bkr Vendor tech Info Process 14.
UIR 350 Recommended Change To Rx Trip Bkr Maintenance FINAL SAFETY ANALYSIS REPORTS CHANGE REQUESTS (FSARCRs) 1.
97-MP3-15* AFW 2.
97-MP3-23 AFW (S.E. developed) 3.
97-MP3-83* RHR lsolation Valves 4,
97-MP3-111 Relief Valves Referenced to Code Case N-242 (S.E. S3-EV-97-0094) 3
i 5.-
97-MP3-144* Sl Pumps Cooling System 6.
97-MP3-254 Containment Analysis Analytical Model(S.E. S3 EV-97-0218) 7.
97-MP3-265* Containment isolation System (related to Mod DCR M3 96062) 8.
97-MP3-289 Safety Evaluation / Reactor Plant Component Cooling System 9.
97-MP3-394 Electric Equipment Not Requiring Internal Cable Separation 10.
97-MP3-080* AFW (S.E. S3-EV-0011)
- Item considered closed by NU EffGINEERING EVALUATIONS and CALCULATIONS 1.
Calc 771 Fuel Pool Cooling & Purification System (related to FSARCR 97-MP3-375) 2.
EWA M3-94159' Review of Piping Systems for HELB 3.
EWR M3 93132*
Revise Calc 188E, Batt Size Cales & Battery Charger Size
- Engineering Effort Considered Complete by NU i
j i
t 4