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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation ML20203B9591997-09-18018 September 1997 Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn ML20210J1761997-07-31031 July 1997 Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept ML20138D1991997-04-0404 April 1997 Special Project97-928S, Sequoyah Nuclear Plant Assessments ML20138C5371997-03-24024 March 1997 Rev 0 to Pressurizer Level Event ML20217G2401997-03-0303 March 1997 Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow ML20117J3611996-08-0101 August 1996 SE of Safety Valve Setpoint Tolerance Relaxation ML20117K9461996-03-0505 March 1996 Reliability Study ML20117K9511996-02-29029 February 1996 Reliability Common Cause Assessment, for Feb 1996 ML20095J1891995-10-0505 October 1995 Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds ML20081D3831995-03-12012 March 1995 Simulator Four Yr Test Rept for 950312 ML20083N9521994-11-16016 November 1994 10CFR50.59 Rept to Nrc ML20024H8491993-07-19019 July 1993 Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles. ML20118D1941992-09-21021 September 1992 Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment ML20114A6641992-08-15015 August 1992 920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period ML20141M1341992-03-27027 March 1992 Spent Fuel Pool Mod for Increased Storage Capacity ML20029C2011991-03-12012 March 1991 Initial Simulator Certification. ML20028H8591990-09-0707 September 1990 Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues. ML20136J0431990-06-30030 June 1990 Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks ML20043B6061990-05-11011 May 1990 Diesel Generator Voltage Response Improvement Rept. ML20006E5771990-02-0505 February 1990 Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis. ML20246D5351989-02-28028 February 1989 Steam Generator Tubing Insp Results ML20247H1301988-11-30030 November 1988 Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns ML20236D1951988-11-18018 November 1988 HVAC Damping Values ML20134H6801988-09-0202 September 1988 Technical Evaluation of Procurement of Matls & Svcs ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20151Q2691988-08-0101 August 1988 Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping ML20155J5721988-07-31031 July 1988 Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway ML20207F6231988-07-0505 July 1988 Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2 ML20207B6301988-06-27027 June 1988 Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program ML20147G9961988-03-31031 March 1988 Review of Operational Readiness Corrective Actions. Related Documentation Encl ML20147H6331988-02-29029 February 1988 Plant,Diesel Generator Evaluation Rept ML20147G7861988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input ML20147G8041988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs ML20234F2111988-01-0505 January 1988 Rept of Sequoyah Readiness Review ML20147F0581987-12-0202 December 1987 Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept ML20236B3481987-10-15015 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation ML20236B3511987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 232.8(B), Piping & Valve Design:Criteria for Min Pipe Wall Thickness ML20236B3541987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 235.2(B), Electrical Safety:Exposed 480 Volt Bus at Panel Top ML20236B3441987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 204.9(B), Use of Reverse Prints ML20236B3581987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector ML20236Q2011987-10-0101 October 1987 Temp Measurement Rept for Long-Term Current Test on Littlefuse,Flas-5,5 Amp Fuses 1999-08-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
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TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-15 SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 0 TITLE: Sequoyah Nuclear Plant Radiological Emergency Plan REASON FOR REVISION: N/A SWEC
SUMMARY
STATEMENT: The items in this report were identified by the Nuclear Regulatory Commission (NRC) and were included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis. All items evaluated within this report were verified to be adequately addressed and were closed by the NRC.
PREPARATION PREPARED BY:
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DATE REVIEWS PEER:
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SIGNATURE DATE CONCURRENCES CEG-H: LD lt/4/f6 SRP: mh ll*l2.'8 SIGNATURE DATE G SIGNATURE
- DATE APPROVED BY' YN 11 ll'l3O AllA ECSP MANAGER DATE MANAGER OF/N0 CLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary's signature denotes SRP concurrences are in files.
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TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT ENPLOYEE CONCERNS TASK GROUP OTHER SITES CEG Element
Title:
SQN Radiological Emergency Plan SWEC Concerns: A02850506006-001
-002 A02841206001-001
-002 Source Documents: NRC Inspection Report 50-327/85-13, 50-328/85-13 and NRC letter dated November 28, 1984 Emergency Plan Deficiencies Report Number: SWEC-SQN-15 Evaluator: ,(. 3aA/, /8!d !fb R. C. Birchell Dat6 Reviewed By: klA4 '
/0[3[(0 J. J. Knightly Date Approved By: emu A.G.Debbag[
/0 [7!fli, Date' 1398T
9 Report SWEC-SQN-15 I. Introduction During an unannounced Nuclear Regulatory Commission (NRC) inspection in the area of emergency preparedness (March 25 through March 29, 1985),
the NRC inspector identified and reported (reference 1) two violations. In addition, NRC issued a letter (reference 2), dated November 28, 1984, identifying two concerns with the Sequoyah Nuclear
' Plant (SQN) emergency plan. These are addressed as issues in the Stone
& Webster Engineering Corporation (SWEC) systematic analysis, as follows: -
- 1. A02850506006-001 (Violation 50-327,328/85-13-02) Failure to Provide t Emergency Response Training to Shift Engineers.
- 2. A02850506006-002 (Violation 50-327, 328/85-13-01) Silent Tests of Sirens not Conducted on Two Week Internals.
j 3. A02841206001-001 Failure to Neet Planning Criteria In NUREG-0654.
- 4. A02841206001-002 Notification by Commercial Broadcasts Per t NUREG-0654.
Information on the background, corrective actions taken, verification methodology, verification analysis, completion status, and pertinent references for these four issues are included in this report.
II. Verification of SWRC Issues A. Background The NRC inspector identitled the following violations:
- 1. 50-127. 328/85-13-02
}
10 CFR 50.54(q) requires that nuclear power reactor licensees j follow and maintain in effect emergency plans which meet the i
requirements of Appendia E to 10 CFR Part 50 and the planning
] standards of 50.47(b). 10 CFR 50.47(b)(15) requires that those 1
' who may be called on to assist in an emergency be provided radiological emergency response training. Section 4.1.1 of the Sequoyah Nuclear Plant (SQN) Radiological Emergency Plan (REP) i states, in part, that it is the responsibility of the Site i Emergency Director to initially make recommendations for protective actions to State and local agencies if necessary.
Section 4.1 of the plan states that the Shift Engineer on duty may be designated the Site Emergency Director and acts for him until relieved.
Contrary to the above, Shift Engineers' performance during walk-through interviews indicated that training was inadequate in the area of protective action decisionmaking.
Page 1 of 5
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Specifically, the Shift Engineers were not capable of consistently determining when and what type of protective action recommendations were appropriate to protect health and safety of the public.
- 2. 50-327, 328/85-13-01 SQN Technical Specifications, paragraph 6.8.1.e specifies, in part, " Written procedures shall be established, implemented and maintained covering the activities referenced below: . . .e.
Site Radiological Emergency Plan implementation." The SQN Radiological Emergency Plan, Section 7.1.12.2 " Fixed Sirens "
states, in part, "the stren system is activated on a monthly basis by Tennessee Emergency Management Agency (TEMA) as a regularly scheduled test. A silent test is conducted every two weeks to test the radio link to the sirens. The silent test advances a counter on each steen if the radio link is complete. TVA employees read the counters on a monthly basis." Contrary to the above, the silent test had not been run every two weeks for approximately seven months but had been included in the monthly test for the ensulas period.
The NBC letter dated November 28, 1984, identified the following two concerns:
- 3. Revision 9 - The review of changes to the REP submitted as revision 9 Indicated that Procedure P-7, " Emergency Equipment and Supplies," has been deleted. This procedure provided for the periodic inspection and maintenance of emergency equipment and supplies. Failure to provide for this is inconsistent with l the specific planning criteria in section II.H.10 of 1
NUREG-0654, which states that each organization shall make provisions to inspect Inventory, and operationally check emergency equipment / instruments at least once each calender l quarter and after each use.
f
) 4. Revision 11. Section 7.1.12. " Prompt Notification Systems " was added to the Plan. This addendum was found to meet the criteria for acceptance in revision 1 of NUREG-0654,
!' appendix 3 section B and 10 CFR 50.47(b)(5)(7), except that notification by commercial broadensts and the contents of the message were not addressed, although the plan states that the tone-elect radlos are placed in institutions. Failure to i provide for this is inconsistent with the specific planning criterla in section II.E.7 of NUERG-0654, which states, in part, that "Each organization shall provide written messages i
intended for the public. . . the role of the licensee is to l provide supporting information for the messages."
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r B. Corrective Action Taken
- 1. A02850506006-001 (Violation 327, 328/85-13-02) Failure to l Provide Emergency Response Training to Shift Engineers
, In response to this violation (reference 3) SQN revised Implementing Procedure (IP)-5, " General Emergency" (reference 4) to ensure consistency with federal guidance for protective action decisionmaking, and a letter was sent to the Shift Engineers and Assistant Shift Engineers describing the changes. The procedure changes for IP-5 were also be*ng reviewed during scheduled licensed operator requalification training.
- 2. A02850506006-002 (Violation 50-327. 328/85-13-01). Slient Tests of Sirens Not Conducted on Two Week Internals SQN provided NRC the following corrective actions in response
] (Keference 3) to this violation:
! TVA and TEMA resumed the original frequency for performing the s11ont test on May 15, 1985.
No additional deviations from the stren test schedule will be
- initiated unless such changes are reflected in the REP.
Individuals responsible for making changes to the REP have been reinstructed on established guidelines for making changes on the REP.
, A letter from TVA to TEMA dated April 22, 1985 documents the decision to resume the two-week silent test frequency.
i
- 3. A02841206001-001 Failure To Neet Planning Criteria In NUREG-0654 This concern deals with revision 9 of the REP. SQN is currently implementing revision 26 to the REP. In addition,
{ four NRC inspections (references 3,5,6, and 7) have been
! performed at SQN in the area of emergency preparedness since I
the issuance of the NRC letter and no violations or deviations were identified in this specific area. No additional concerns on planning criteria for NUREG-0654 compliance have been identified by the NRC on later REP revisions.
i
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- 4. A02841206001-002, Notification By Commercial Broadcasts Per NUREG-0654 This concern deals with revision 11 of the REP. As stated
' previously, SQN is implementing revision 26 to the REP and four inspections (references 3, 5, 6 and 7) hsve been performed in l this area with no violations or deviations identified.
Page 3 of 5
7-C. Verification Methodology The SWEC concerns identified for Employee Concerns Task Group (ECTG) verification were stated as follows:
RIMS ISSUE RIMS ITEM A02850506006 Failure to provide emergency RIMS-001 response training to shift engineers.
A02850506006 Silent test of strens not RIMS-002 conducted on two week intervals RIMS ISSUE RINS ITEM A02841206001 Failure to meet planning RIMS-001 criteria in NUREG-0654 A02841206001 Notification by commercial RIMS-002 broadcasts per NUREG-0654 BCTG reviewed the SQN Compliance Licensing files for internal and external correspondence related to this issue, the applicable procedure, and the NRC status and tracking system for the issues.
This review of the pertinent documentation formed the basis for this verification activity.
D. Verification Analysis The ICTG review indicated that the two violations and two concerns were adequately resolved. The corrective actions for violations 50-327, 328/85-13-01 and 50-327, 327/85-13-02 were found acceptable to the NRC. Violation 50-327, 328/85-13-01 was closed in NRC report 85-41 (reference 6) and violation 50-327, 328/85-13-02 was closed in NRC report 86-03 (reference 7).
E. Completion Status - Based on SQN corrective action, compliance with requirements, and NRC closure of the items, no further actions on these items is required. These SWEC concerns are closed.
t l
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III. References
- 1. NRC Inspection Report Number 50-327, 328/85-13 dated May 3, 1985, Roger D. Walker to H. G. Parris
- 2. NRC letter, " Emergency Plan Deficiencies - Sequoyah Nuclear Plant,"
dated November 28, 1984, John A. 01shinski to H. G. Parris
- 3. Response to NRC Inspection Report Number 50-327, 328/85-13, dated June 3, 1985, J. A. Domer to Dr. J. Nelson Grace
- 4. SQN RRP Implementing Procedure (IP)-5, " General Emergency"
- 5. NRC Inspection Report Number 50-327, 328/85-07, dated February 27, 1985, Daild M. Vercelli to H. G. Parris
- 6. NRC Inspection Report Number 50-327, 328/85-41, dated December 19, 1985, David M. Vercelli to H. G. Parris
- 7. NRC Inspection Report Number 50-327, 328/86-03, dated February 3, 1986, David M. Vercelli to S. A. White i
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