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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 ML20205E2361999-03-31031 March 1999 Mnps,Units 1,2 & 3 Decommissioning Funding Status Rept ML20204K1031999-03-19019 March 1999 Non-proprietary Licensing Rept for Spent Fuel Rack Installation at Mnps,Unit 3 ML20207B2271999-02-22022 February 1999 Rev 0 to SIR-99-021, Evaluation of Stratification Loadings in LBB Analysis for Mnps,Unit 2 Surge Line ML20199D4571999-01-0808 January 1999 Progress Toward Restart Readiness at Millstone Unit 2 - Nu Briefing for Nrc ML20197H5871998-12-31031 December 1998 Independent Corrective Action Verification Program, Final Rept,Vol 1 ML20198G7161998-11-30030 November 1998 Rev 0 to EMF-2145, Millstone Unit 2 Large Break Loca/Eccs Analysis with Replacement SGs & Plant Modifications ML20195H7401998-11-30030 November 1998 Station/Unit 3 Third Quarter Performance Rept ML20195C8091998-11-0909 November 1998 Request for Permission to Apply LBB Methodology to Pressurizer Surge Piping, Plant Specific Info Fo Pressurizer Surge Piping ML20195C7731998-10-13013 October 1998 Rev 0 to SIR-98-096, Pressurizer Surge Line LBB Evaluation Mnps,Unit 2 ML20198G7041998-09-30030 September 1998 Rev 0 to EMF-2079, Millstone Unit 2 Large Break Loca/Eccs Analysis with Replacement Sgs ML20154P9541998-09-30030 September 1998 Simulator Quadrennial Certification Rept ML20237B4781998-07-31031 July 1998 Station/Unit 3,Second Quarter Performance Rept for Jul 1998 ML20237B2801998-07-31031 July 1998 Rev 1 to EMF-98-036, Post-Scram Main Steam Line Break Analysis for Millstone Unit 2 ML20236V7541998-07-0101 July 1998 Rev 0 to Little Harbor Consultants,Inc, Evaluation of Millstone Self-Assessment & Independent Oversight Programs ML20236U6361998-07-0101 July 1998 Rev 0 to Leak-Before-Break Evaluation High Energy Safety Injection Piping,Mnps,Unit 2 ML20236F5221998-06-30030 June 1998 Independent Assessment of Upper Guide Structure (Ugs) Personnel Contamination Event at Millstone Station Unit 2, Final Rept ML20236F5051998-06-25025 June 1998 Rev 1 to Event Review Team Rept Root Cause Investigation Upper Guide Structure (Ugs) Personnel Contamination Event ML20249C3911998-06-22022 June 1998 Simulator Quadrennial Certification Rept ML20248F4071998-06-0101 June 1998 Final Rept SL-5192, Independent Corrective Action Verification Program for Millstone Unit 3 ML20236P4341998-05-22022 May 1998 Progress Toward Restart Readiness at Millstone Station - Northeast Utilities Briefing for Nrc ML20236F6411998-05-11011 May 1998 Rev 0 to Justification of Continued LBB Compliance for Nu MP2 ML20203H3531998-02-24024 February 1998 Transport of Small Air Pocket ML20216E0961998-02-17017 February 1998 Redacted Safety Conscious Work Environment (Assessment of Nuclear Oversight 980121 Statement) ML20199G8031998-01-31031 January 1998 Radiological Survey for Waterford Town Landfill,Waterford, Ct ML20199D9111998-01-23023 January 1998 Independent Corrective Action Verification Program Status Rept, for Period Ending 980123 ML20203H3961997-12-31031 December 1997 Integrated Sys Functional Review for Mnps,Unit 3, Engineering Self Assessment Rept ML20217C2201997-12-16016 December 1997 Exam of Concrete Cores Millstone III Subcontainment Porous Concrete ML20202H2981997-12-0202 December 1997 Independent Corrective Action Verification Program Status Rept ML20203H3661997-11-30030 November 1997 Transient Clearing of Air in Loop Seal ML20199G8091997-11-30030 November 1997 Radiological Survey for Equestrian Ctr Harkness State Park Waterford,Ct ML20211F7171997-09-29029 September 1997 Rev 0 to Critical Design Characteristics Radiological Events for Millstone 2 ML20217F9481997-08-31031 August 1997 Non-proprietary Version of Bases for Millstone Unit 3 ECCS Current & Future Ts ML20217Q7101997-08-29029 August 1997 Rev 0 to Critical Design Characteristics Reactivity Events ML20217Q7181997-08-29029 August 1997 Rev 0 to Critical Design Characteristics Undercooling Events & Reactor Coolant Flow Reduction Events ML20210H0051997-08-0505 August 1997 Rev 0 to Critical Design Characteristics Reactor Coolant Pressure Boundary Events & Mslb/Loca Containment Analyses ML20149F0971997-07-18018 July 1997 Rev 0 to Critical Design Characteristics Overcooling Events,Millstone 2 ML20148Q2901997-06-24024 June 1997 Simulator Quadrennial Rept for 1993-1997 ML20148K8221997-05-31031 May 1997 Temporary Use of Atlas Copco Diesel Compressor PTMS900 at Millstone Nuclear Power Station Unit 3 Maint of Svc Air Sys ML20148R7151997-05-30030 May 1997 Progress Toward Restart Readiness at Millstone Station ML20210S3711997-04-29029 April 1997 Margin of Immunity Determination for SRV Electric Lift for Neut,Millstone Nucelar Site,Unit 1 ML20138E6391997-04-11011 April 1997 Investigation of Possible Deterioration of Porous Concrete Millstone 3 Nuclear Reactor ML20217C2121997-04-0707 April 1997 Rev 2 to S3-EV-9700574, SE for Containment Structure Porous Concrete Drainage Sys ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20138E6471997-03-14014 March 1997 Porous Concrete Investigation Millstone 3 Waterford,Ct ML20137C6281997-03-14014 March 1997 Redacted Version of Rev 1 to Nuclear Training Loit/Lout Audit Reviews ML20141D2881997-02-17017 February 1997 Rev 3 to Maint Rule Unit Basis Document ML20135E3221997-02-13013 February 1997 Independent Review Team Rept 1996 MP -1 Lout NRC Exam Failures ML20133C1451996-12-31031 December 1996 Porous Concrete Mock-Up Testing Phase III W/Containment Mat Concrete 1999-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
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Page 25 Table 1-1 (cont'd) .
Millstone Unit III uses other qualified items other than those appearing on the Class 1E Master List.
These items are not identified by unique equipment ID because of their extensive usage throughout the plant. These items have been qualified to the worst case environmental condition (inside containment) to support their usage for anywhere at Millstone Unit III.
The following list of items are used by construction through engineerirg disposition in order to ensure that their intended application is justified. The supporting documentation can be found filed under Specification 2400.000-350,
- 1. Raychem Heat Shrink Tubing (WCFS-N)
- 2. Marathon Terminal Blocks (1500/1600-N series)
(Terminal Blocks are used only outside of containment for Class 1E circuits)
- 3. General Electric SIS Vulkene Supreme Wire
- 4. ITT Supernaut SIS Wire
- 5. Anaconda SIS Wire
- 6. Rockbestos Firewall III SIS Wire
- 7. Brand-Rex SIS Wire Millstone Unit III also utilizes only qualified cable. This cable, like the above mentioned items, does not have a unique equipment ID found on the Class IE Master List.
The following is a list of cable suppliers for cable found at Millstone Unit III:
- 1) Anaconda A) High temperature cable 2412.400-694
- 2) Boston Insulated Wire A) 600 V Instrument Cable 2412.400-255 B) Triaxial Cable 2412.400-257 C) Thermocouple Extension Wire 2412.400-258
- 3) Kerite A) 1000 V Power Cable 2412.300-253 B) 5000 V Power Cable 2412.300-239 C) 8000 V Power Cable 2412.300-239
- 4) Okonite ,
A) 1000 V Control Cable 2412.400-645 7E) These cables are used extensively throughout the plant and are qualified for the worst case environmental C>e
~
condition (inside containment).
Q cCL, Revision 2 8509160323 850831 A"E"**
- PDR ADOCK 05000423 A PDR
- MNPS-3 EEQ been qualified to the dose resulting from a fuel handling s accident. .
2.1.6 Margins (NUREG-0588 Item 3.) !
The analysis from which the qualification envelopes are constructed is inherently conservative. Assumptions regarding initial conditions ;
and various other inputs typically are made to maximize the parameter i of interest.
The containment pressure / temperature envelope curves are composites l developed from environmental transients for several LOCAs and MSLBs. l The enveloping procedure increases both the temperature / pressure ;
peaks and the time spans. The resulting envelope curve is ;
significantly more conservative than any single curve. (
The HELB envelopes developed for building zones outside containment were constructed in a similar manner to those for inside containment. !
Where multiple break cases exist, composite envelopes are developed. }
Additional margin is added in constructing the envelope. !
A significant margin exists in the spray environment pH specified for equipment inside containment. The maximum calculated pH of the spray
, environment is 8.3; 10.5 is specified on the equipment specification data sheets. !
i For the radiation doses, a safety margin of two has been applied to all the accident doses. Except as noted on the SCEWs, the equipment ,
(' has been qualified to the maximum dose in the applicable area. ;
Location specific doses are generally much lower. One percent failed .
4 fuel has been considered for normal operation doses which is i significantly greater than the expected amount of fuel failure.
l 2.2 IDENTIFICATION OF SYSTEMS f I g 2.2.1 System Safety Functions I j As part of the evaluation of environmental qualification of Class 1E equipment, systems have been categorized in terms of the following j safety functions: ,
t
- 1. Emergency reactor shutdown f t
j 2. Containment isolation i i I 6
- 3. Reactor core cooling i l
i i
- 4. Containment heat removal '
- 5. Core residual heat removal l
- 6. Prevention of significant release of radioactive material to ['
the environment s_ -
Revision 2 2-5 August 1985 i l
l L __
HNPS-3 EEQ
- 7. Support and other equipment This categorization is shown in Table 2-1.
System and building abbreviation codes used on the master list are listed in Table 2-2 and are also included under the worksheet tab of the Worksheets book for ease of reference.
2.2.2 Operating Time Considerations Qualification operating times have been chosen based on the length of time equipment must perform its safety function when subjected to the limiting environmental conditions.
2.2.3 Methodology - Evaluation of Electrical Equipment The qualification program includes all safety-related electrical (Class lE) equipment which must function to mitigate the consequences of an accident. To implement the program, each specification /purchast. order containing safety-related electrical equipment was identified, and qualification program requirements were placed on each vendor for applicable equipment. Qualification program requirements were also implemented for field purchased items, such as cables. Vendor programs were evaluated using the steps illustrated on the Environmental Qualification Review Flowchart (Figure 2-1). Checklists were developed to provide a systematic review of all aspects of a vendor's qualification test report.
In addition, the components of each system were reviewed on the basis of the system safety functions identified in Section 2.3. The result was a list, by system, of equipment required for inclusion in the qualification program. The system list was correlated with the equipment list by specification, thus assuring the inclusion of all required equipment in the qualification program.
The qualification goal of the program was to qualify each item of identified equipment for the most severe envi onment for location of the equipment, regardless of safety funct.on. Thus, an equipment item outside containment, required to function for only LOCA, is nevertheless qualified for a high energy line break environment.
Segregation of system safety function and environments was only used where qualification to the maximum environment could not be attained.
If qualification could not be obtained, an evaluation was performed to demonstrate that failure of such equipment would not be detrimental to plant safety or accident mitigation or mislead the operator.
2.2.4 Qualification Documentation Review Qualification documentation review is a joint effort between NUSCo and SWEC. A review is conducted on each procurement specification that identifies EEQ devices (equipment).
The review consists of the following steps:
Revision 1 2-6 July 1985 L )
t$~
, INTEROFFICE MEMORANDUM gogog,
- Ae.
SUBJECT Millstone 3 EEQ Report, DATE August 30, 1985 Revision 2 FROM WFEmerson TO oireu . Neueo ae u- cc AMWalker 1 Regulation U.S. Nuclear Regulatory Ccamission 7920 Norfolk Avenue Bethesda. MD 20014 A!!N: DCC MENT CONTROL OESK -
The attached pages constitute Revision 2 to the Millstone 3 Environmental Qualification of Electrical Equipment Report.
Please insert Table 1-1 (page 25) in your manual after pages 23/24.
Also, remove from your manual pages 2-5/2-6 and insert the attached replacement copies in their place. >
This memorandum should be filed behind the frontispiece in your volume in front of any existing letters or instructions.
Thank you.
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