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Category:NRC TECHNICAL REPORT
MONTHYEARML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20246D9051989-08-31031 August 1989 Staff Evaluation of Dispute Between Case & TU Electric on Acceptability of Jul 1982 RCS Cold Hydrostatic Test ML20238A7261987-09-0303 September 1987 Partially Withheld Rept of Interview W/W Clements Re Internal Investigation Into Allegation of Intimidation of QA Audit Group NUREG-1257, Review of Issues Raised by Oia Rept 86-10 Concerning Comanche Peak Steam Electric Station:Rept of Comanche Peak Rept Review Group1987-03-31031 March 1987 Review of Issues Raised by Oia Rept 86-10 Concerning Comanche Peak Steam Electric Station:Rept of Comanche Peak Rept Review Group ML20238A9231987-03-0606 March 1987 Rept Review Group Task 1 Review Group Rept ML20238A7821987-03-0303 March 1987 Rept by 766 Task Group to Comanche Peak Rept Review Group ML20238A8831987-02-27027 February 1987 Rev 1 to Comanche Peak Rept Review Group Task 2 Rept for 870120-0227 ML20238A7191987-02-26026 February 1987 Draft Rev 1 to Comanche Peak Rept Review Group Task Group 3 Rept of Safety Significance ML20238A6671987-02-18018 February 1987 Draft Rev 0 to Comanche Peak Rept Review Group - Task Group 3 Rept ML20238B4951987-02-17017 February 1987 Draft Rept by 766 Task Group to Comanche Peak Rept Review Group ML20238B3521987-02-13013 February 1987 Draft Comanche Peak Rept Review Group Task 1 Rept ML20238A6091987-02-11011 February 1987 Draft Rev 0 to Comanche Peak Rept Review Group Task 2 Rept for 870120-0210 ML20215C8221986-12-11011 December 1986 Partially Withheld Rept of Investigation Re Allegations of Misconduct by Region IV Mgt W/Respect to Plant ML20207A9801986-10-30030 October 1986 Evaluation Supporting Util 840925 Submittal Re Lesser Separation Between Class 1E & Certain non-Class 1E Circuits. Analysis Provided Justifies Lesser Separation Between Circuits ML20211M2371986-02-13013 February 1986 Morning Rept:On 860212,bomb Threat Received at Util.Nuclear Engineering Bldg Evacuated.Personnel Returned to Work Following Site Security Search.Corporate Security Investigating Matter IA-86-208, Morning Rept:On 860212,bomb Threat Received at Util.Nuclear Engineering Bldg Evacuated.Personnel Returned to Work Following Site Security Search.Corporate Security Investigating Matter1986-02-13013 February 1986 Morning Rept:On 860212,bomb Threat Received at Util.Nuclear Engineering Bldg Evacuated.Personnel Returned to Work Following Site Security Search.Corporate Security Investigating Matter ML20210K9741986-01-24024 January 1986 Status Briefing Re Comanche Peak Technical Review Team Program Plan,Fsar Review & Allegations to Enable Completion of All Sser Sections ML20134A7571985-10-31031 October 1985 Rept of Review & Evaluation of Allegations of Intimidation & Harassment of Employees at Comanche Peak Steam Electric Station,Units 1 & 2 ML20215F0901985-10-29029 October 1985 Rept of 851029 Reinterview W/J Marshall Re Involvement W/Mgt Analysis Co Rept ML20133C7271985-09-30030 September 1985 Rev 2 to Staff Evaluation of Comanche Peak Response Team Program Plan:Detailed Comments/Concerns ML20199E6571985-09-27027 September 1985 Population Items List, Fuel Pool Liner ML20199E3031985-09-26026 September 1985 Rev 1 to Population Description, Large Bore Pipe Welds/ Matl ML20199G7091985-09-25025 September 1985 Population Items List, Large Bore Pipe Welds/Matl. Related Info Encl ML20199E6401985-09-13013 September 1985 Population Items List, Small Bore Piping & Instrument Tubing/Piping Welds/Matl ML20199E6321985-09-0606 September 1985 Population Items List, Concrete Placement ML20199E6441985-09-0505 September 1985 Rev 0 to Population Items List, Mechanical Equipment Installation. Related Info Encl ML20199E6261985-08-21021 August 1985 Rev 0 to Population Items List, Piping Sys Bolted Joints/ Matl. Related Info Encl ML20199E5861985-08-17017 August 1985 Rev 2 to Population Description, Field Fabricated Tanks ML20199E6811985-08-14014 August 1985 Rev 0 to Population Items List, Small Bore Piping Configuration ML20199E5731985-08-14014 August 1985 Population Items List, Liners ML20136G4131985-08-0909 August 1985 Rev 2 to Staff Evaluation of Comanche Peak Response Team Program Plan ML20199E5601985-08-0909 August 1985 Rev 0 to Population Description, Mechanism Equipment Installation. Related Info Encl ML20199E2951985-08-0808 August 1985 Population Description, Liners ML20215F1711985-08-0505 August 1985 Rept of 850730 Interview W/R Tolson in Dallas,Tx Re Withholding of 1978 Mgt Analysis Co Rept ML20215F1051985-08-0505 August 1985 Rept of 850802 Interview W/R Spangler in Dallas,Tx Re Knowledge of Mgt Analysis Co Rept ML20199E5541985-08-0505 August 1985 Population Description, Concrete Placement ML20215F0991985-08-0505 August 1985 Rept of 850802 Interview W/D Anderson in Dallas,Tx Re Knowledge of 1978 Mgt Analysis Co Rept ML20215F0541985-08-0505 August 1985 Rept of 850802 Interview W/Ss Palmer in Dallas,Tx Re Knowledge of 1978 Mgt Analysis Co Rept ML20215F0051985-08-0505 August 1985 Rept of 850802 Interview W/Tw Rose in Dallas,Tx Re Involvement W/Mgt Analysis Co Rept ML20210D4591985-07-31031 July 1985 NRC Plan for Review & Audit of Applicants Program for Assuring Design & Const Adequacy of Comanche Peak Steam Electric Station ML20199E5291985-07-30030 July 1985 Rev 1 to Population Items List, Large Bore Pipe Supports - Rigid. Related Info Encl ML20199E6141985-07-29029 July 1985 Rev 0 to Population Items List, Field Fabricated Tanks. Related Info Encl ML20199E6511985-07-23023 July 1985 Rev 1 to Population Description, Large Bore Pipe Supports - Nonrigid. Related Info Encl ML20199E5381985-07-23023 July 1985 Rev 1 to Population Description, Large Bore Pipe Supports - Rigid ML20199E6691985-07-22022 July 1985 Population Description, Fuel Pool Liners. Related Info Encl ML20199E2321985-06-26026 June 1985 Rev 0 to Population Description, Small Bore Piping & Instrument Tubing/Piping Welds/Matl ML20199E2401985-06-26026 June 1985 Population Description, Piping Sys Bolted Joints/Matls ML20199E2681985-06-26026 June 1985 Rev 0 to Population Description, Large Bore Pipe-Welds/ Matl ML20199E2821985-06-26026 June 1985 Rev 0 to Population Description, Large Bore Piping Configuration ML20199E2491985-06-25025 June 1985 Rev 0 to Population Description, Small Bore Piping Configuration 1993-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E8021999-10-0707 October 1999 CPSES Unit 1 Cycle 8 Colr ML20217G4151999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Cpses,Units 1 & 2 ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20216J5701999-09-16016 September 1999 Rev 2 to CPSES Unit 2 Cycle 5 Colr TXX-9920, Monthly Operating Repts for Aug 1999 for Cpses.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Cpses.With ML20211M2981999-08-0606 August 1999 Rev 1 to CPSES Fuel Storage Licensing Rept, CPSES Credit for Soluble Boron & Expansion of Spent Fuel Storage Capacity, Consisting of Revised Title Page and 4-1 ML20210U4081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Cpses,Units 1 & 2 ML20210D8321999-07-23023 July 1999 Safety Evaluation Accepting Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20209H7661999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209H2721999-07-0909 July 1999 2RF04 Containment ISI Summary Rept First Interval,First Period,First Outage ML20209H2631999-07-0909 July 1999 2RF04 ISI Summary Rept First Interval,Second Period,Second Outage ML20209G7501999-07-0808 July 1999 SER Finding That Licensee Individual Plant Exam of External Events Complete with Regard to Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given Design, Operation & History of Comanche Peak Steam Electric Station ML20196L0191999-07-0808 July 1999 Safety Evaluation Granting Request Relief B-6 (Rev 2),B-7 (Rev2),B-12,B-13,B-14 & C-9,pursuant to 10CFR50.55a(g)(6)(i).Technical Ltr Rept Also Encl ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20209G0801999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Cpses,Units 1 & 2 ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively ML20195G5141999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Comanche Peak Steam Electric Station,Units 1 & 2.With ML20216E0711999-05-21021 May 1999 1999 Graded Exercise - Comanche Peak Steam Electric Station ML20206Q0091999-05-14014 May 1999 Safety Evaluation Accepting GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Electric Station,Unit 1 ML20206H2061999-05-0606 May 1999 SER Accepting Exemption to App K Re Leading Edge Flowmeter for Plant,Units 1 & 2 ML20196L2241999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Cpses,Units 1 & 2 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205J7831999-04-0101 April 1999 Rev 0 to ERX-99-001, CPSES Unit 2 Cycle 5 Colr ML20205N3101999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Cpses,Units 1 & 2 ML20204H6371999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Comanche Peak Units 1 & 2 ML20205N1481999-02-28028 February 1999 Corrected Monthly Operating Rept for Feb 1999 for CPSES, Units 1 & 2 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 ML20210J9201999-02-0101 February 1999 CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802- 990201 ML20202D0101999-01-27027 January 1999 Safety Evaluation Supporting First 10-yr Interval ISI Program Plan Requests for Relief B-9,B-10 & B-11 for CPSES, Unit 1 ML20199E9961998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Cpses,Units 1 & 2 ML20207D6091998-12-31031 December 1998 1998 Annual Operating Rept for Cpses,Units 1 & 2. with ML20197K2371998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Cpses,Units 1 & 2 ML20195F3161998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Cpses,Units 1 & 2 ML20154M8841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Cpses,Units 1 & 2 ML20154B5741998-09-30030 September 1998 Safety Evaluation Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves. Licensee Has Established Acceptable Program ML20151W0361998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Cpses,Units 1 & 2. with ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20237C6721998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Cpses,Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236R0711998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Cpses,Units 1 & 2 ML20249B2581998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Cpses,Units 1 & 2 ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20247G3241998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Cpses,Units 1 & 2 ML20216B8661998-04-0101 April 1998 Rev 0 to ERX-98-001, CPSES Unit 1 Cycle 7 Colr ML20216J3061998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Cpses,Units 1 & 2 ML20216J1861998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Comanche Peak Steam Electric Station ML20197A6951998-02-24024 February 1998 Inservice Insp Summary Rept,First Interval,Second Period, First Outage ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 1999-09-30
[Table view] |
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- 1. Allegation Category: QA/QC 3, Records
- 2. Allegation Number: AQ-49, AQ-74 and AQ-125
- 3. Characterization: It is alleged that permanent QA/QC construction, fabri-cation, installation, and inspection records were lost during various stages of record completion.
- 4. Assessment of Safety Significance: Because these allegations were general in nature, the NRC Technical Review Team (TRT) assessed them for both iso-lated and generic. implications. The alleger's concerns addressed the loss or misplacement of QA/QC records which documented inprocess and completed fabrication and inspection activities performed at Unit 1. These records typtr: ally documented activities for welding, process control, inspection, installation, testing, nonconformance, and corrective action disposition.
Allegations AQ-49 and AQ-74 addressed the loss of individual weld data cards, a: well as the possible loss of hundreds of entire documentation packages for ASME Code hanger. The specific weld data card cited was CC-1-087-004-A33A. Typically, a documentation package contains weld data cards, inprocess and final inspection reports, drawings, vendor documenta-tion, nonconformance reports (NCRs), and ASME Code data reports. In an interview with the TRT, the alleger disclosed that the lost records were apparently found. Notwithstanding the resolt. tion of the alleger's con-
- cerns, the TRT assessed the potential loss of QA/QC records for generic implications.
In mid-1983, a joint Texas Utilities Electric Company (TUEC) and Brown &
Root (B&R) task force was organized for the control and management of ASME componentsupports(hangers). The task force mission was to verify that design, fabrication, installation, inspection documentation, and assembly activities were performed adequately and in the correct sequence. Part of the task force responsibilty was to initiate 'and/or track documentation packages. ASME Code,Section III, subsection NA, requires that ASME in-sta11ations and hardware be certified in accordance with Code requirements.
At Comanche Peak Steam Electric Station (CPSES), this effort included assuring that QA/QC records were generated and completed to support con-struction and inspection activities. In addition, the ANI (the Authorized Nuclear Inspector, an independent third party) was required to review, concur, and approve ASME documentation / records requiring certification.
Prior to certification, the records were placed in the construction records vault. To assure adequate control of the records, appropriate processing was established to prevent unauthorized removal from and updating to docu-mentation packages in the vault. If documentation could not be located during record's inspection prior to certification, an NCR was generated and resolved in accordance with approved procedures. The dispositioning of NCRs has resulted in the removal of hangers and piping (or portions thereof) and their replacement.
Of the approximately 17,000 ASME Code pipe supports for Unit 1, 15 have been totally or partially refabricated because of lost records. (The reconstruction of weld data cards is addressed in allegation AQW-67 of Mechanical and Piping Category 25 and allegation AQ-67 of Mechanical and
, - - _ ~ . _ _ . _ . . . . _ _ _ . . .
860512 4- 0-105 s emose5-e,_.. ran i ,
Piping Category 8 in " Safety Evaluation Report Related to the Operation of Comanche Peak Steam Electric Station" (NUREG-0797, Supp. No. 10). The reconstruction of the lost weld data card (No. CC-1-087-004-A33A) cited in this allegation was reviewed and found acceptable by the TRT. The method used for examining records accountability for support hangers was also used for ASME piping and related hardware.
- i. l For non-ASME documentation, a similar verification program was established
, for Unit 1. Non-ASME documentation deficiency resolution was accomplished either by constructing new records from reinspection and supporting docu-
.1
. mentation or by hardware removal and replacement.
Allegation AQ-125 concerns construction travelers that were possibly lost by the paper flow group (PFG). Construction travelers were issued to the
' craft personnel and controlled by the PFG. Included in the packages were fabrication, inspection, vendor documentation and other supporting docu-i mentation. Excluded were design documents, such as drawings, component modification cards (CMCs), and design change authorizations (DCAs) which p were provided by the document control center or satellite.
i i
Traveler packages were prepared in accordance with B&R procedure CP-CPM 6.3,
' Revision 10, " Preparation, Approval, and Control of Operational Travelers."
The PFG listed package items in the computer data base as inprocess and completed an inventory card identifying each document in the package. When i
the. package was issued, the inventory card was removed, the name of the person to whom it was issued was entered as the package holder, and the card was filed in the package " outstanding" file to account for the package.
4 The contents of the documentation package were checked against the inventory i
card by PFG personnel prior to issuance and again upon return or completion ,
of work to' assure required documentation was present and correct to the cur-
['
rent revision. Under normal conditions, packages were issued ~at the begin-ning of each work shift and returned at.the close of the shift. Completed
[ packages were forwarded to the QA/QC records review group for final QA/QC review. The data base was then updated'to reflect its completed status.
For documents found missing during the PFG inventory of package contents, an NCR was written to document the discrepancy and to initiate corrective
-action.
Each new or transfered PFG employee received training that covered job responsibilities, scope of work, specific assignments, and procedures directing work activities. On-the-job training was also given until the
[ employee was adequately trained to function independently of supervision.
, The TRT' reviewed documentation verifying that PFG personnel received this indoctrination and training.
J In assessing AQ-125, the TRT determined that PFG personnel had received adequate classroom and on-the-job training to be competent in performing i their work. Because of the self regulating document accountability system, t
.any loss of records would have been detected by the PFG, as previously
- described.
+
l l
, 0-106 1
l
- 5. Conclusion and Staff Positions: The TRT evaluated TUEC's and B&R's proce-dures governing permanent QA/QC records, accountability, and preservation and found them to be in compliance with the ASME Code, 10 CFR Part 50, Appendix B, and ANSI N45.2 requirements. Procedure implementation was verified by TRT reviews of documents and records supporting the construc-tion and inspection activities for selected ASME hangers, components, and piping. Document deficiencies relating to the partial ar complete loss of work packages were reported on NCRs for corrective action. In these cases, reconstruction or replacement of lost records was done in accordance with approved procedures. Such documentation was subject to the same review and approval as the original records received. Accordingly, an effective program exists for the accountability of permanent records supporting construction and inspection at CPSES.
The TRT found that the allegations that construction, fabrication, instal-lation, and inspection records were lost has been substantiated. However, the losses were not of the magnitude first alleged, (i.e., " hundreds" of; entire documentation packages), nor were losses attributable to the lack of competence of the PFG. 'Accordingly, these allegations do not have generic implications.
On December 10, 1984, the TRT met with the alleger and presented the AQ-74 findings and conclusions. The alleger presented further examples of lost document packages. These document packages were a part of the review conducted by TRT, as reported above. The alleger associated with AQ-49 declined further contact with TRT, thus no meeting was conducted. The source of AQ-125 was not an alleger.
- 7. Attachments: None.
Reference Documents:
> 1. ASME Section III, " Nuclear Power Plant Components."
- 2. ANSI N 45.2, "QA Program Requirements for Nuclear Faci M tics."
- 3. ANSI N 45.2.9, " Requirements for Collection, Storage,'and Maintenance of QA Records for Nuclear Power Plants."
- 4. Procedu'res :
- a. QI-0AP-11.1-25, Rev. 8, "QA Review of ASME III Documentation."
- b. CP-QAP-12.1, Rev. 11, "ASME Section III Installation, Verification, and N-5 Certification."
- c. CP-QAP-11.1-28, Rev. 25, " Fabrication and Installation Inspection of Safety Class Components."
0-107
- d. CP-QAP-18.2, Rev. 3, " Quality Assurance Review of ASME Documentation."
- e. CP-QP-18.2, Rev. 2, " Implementation of the Permanent Plant Records Management System."
- f. FP-QP-18.3, Rev. 2, " Permanent Plant Records Systems Organization."
- g. CP-QP-18.4, Rev. 2, " Permanent Plant Records Receipt Control and Storage." ,
- h. CP-QP-18.5, Rev. 2, " Automatic Records Management System Implementation."
- i. CP-QP-18.6, Rev. 2, " Record Turnover to TUGC0 Operations Group."
J. CP-QP-18.7, Rev. 9, "N-5 and N-3 Code Data Reports."
- k. CP-QP-18.8, Rev. 1, " Records Verification."
- 1. CP-QAP-11.1, Rev. 3, " Fabrication and Installation Inspection of Components, Components Supports, and Piping."
- m. CP-QAP-16.1, Rev. 20, " Control of Nonconforming Items."
- n. CP-QAP-12.1, Rev. 8, " Inspection Criteria and Do.cumentation Requirements Prior to System N-5 Certification."
- o. CP-QAP-18.1, Rev. 2, " Processing QA Records."
- p. CP-CPM 7.1, Rev. 1, " Package Flow Control," and Appendices 7.1A through 7.11.
- q. CP-CPM 6.3, Revision 10, " Preparation, Approval, and Control of Operation Travelers."
- 5. NCRs M-12988, M-12997, M-12820, M-12807, M-7368, M-6953, M-7370, M-7371, M-10156, M-10403, M-12816, M-10814, M-7369, M-7372, M-10419, M-13319, M-13241, M-13566, M-6440, M-6435, M-9767, M-14560.
- 6. AQ-49; Interviews with alleger A-13, page 20, and alleger A-1, pages 4 and 9, dated August 1, 1984.
- 7. AQ-74; A-1 Statement, A-1 Interview pages 24-37, dated April 6, 1984, A-1 Interview pages 4-9 dated August 1, 1964, TUGC0 letter TXX4180 (B. R. Clements to D. G. Eisenhut) dated May 25, 1984.
- 8. AQ-125; NRC Special Review Team Report, dated July 13, 1984, page 70.
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6 J 8.
This statement prepared by:
V. Wenczel,viRT
.Date
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Technical: Reviewer Reviewed by: / wat H. Livermore, hDate k [
Group Leader Approved by; V. Noonan, Date Project Director F
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