SER Finding Facility Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 3,except for Accumulator Tank Level & Pressure Instrumentation,Containment Sump Water Temp Instrumentation & Quench Tank Temp InstrumentationML20215G169 |
Person / Time |
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Site: |
Seabrook, 05000000 |
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Issue date: |
06/11/1986 |
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From: |
NRC |
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To: |
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Shared Package |
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ML20213F414 |
List: |
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References |
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FOIA-87-213, RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, NUDOCS 8706230147 |
Download: ML20215G169 (6) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D1461999-09-17017 September 1999 SER Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20210Q7581999-08-11011 August 1999 SER Approving Proposed Merger of CES & Bec,Which Will Create New Parent Company of Canal ML20210J8681999-08-0303 August 1999 SER Approving License Transfer from Montaup Electric Co to Little Bay Power Corp & Approval of Conforming Amend for Seabrook Station Unit 1 ML20205C1981999-03-24024 March 1999 Safety Evaluation Concluding That Proposed Relief Request IR-8,Rev 1,provides Acceptable Alternative to ASME Code Requirements.Recommends Authorization of Proposed Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20196F5741998-12-0202 December 1998 Safety Evaluation Concluding That Licensee Has Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Seabrook ML20197A7531998-02-27027 February 1998 Safety Evaluation Accepting License Request for Relief from ASME Code,Section IX Requirements Re Inservice Insp of RHR Heat Exchanger Nozzle Welds & Reactor Vessel Closure Head Nuts ML20137T9941997-04-0909 April 1997 Safety Evaluation Accepting Proposed Use of ASME Code Case N-524 for North Atlantic Energy Service Corp,Seabrook Station,Unit 1 ML20133P9121997-01-22022 January 1997 Safety Evaluation Accepting Corporate Restructuring of Great Bay Power Corp & Formation of Holding Company,North Atlantic Energy Svc Corp ML20059J2381993-11-0505 November 1993 Safety Evaluation Accepting 921125 TS Changes,Augmented by 930702 Response to NRC Rai,Allowing Use of Fixed Incore Detector Sys at Facility ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20247N5901989-07-28028 July 1989 Safety Evaluation Concluding That Overall State of Onsite & Offsite Emergency Preparedness Provides Reasonable Assurance That Adequate Protective Measures Can & Will Be Taken in Event of Radiological Emergency at Plant ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20245A9091989-06-15015 June 1989 SER Supporting Util Actions to Comply W/Atws Rule (10CFR50.62),pending Resolution of Tech Spec Issue.Licensee Should Continue W/Scheduled Installation & Implementation of ATWS Design Using Administrative Controlled Procedures ML20246H5711989-05-0303 May 1989 Safety Evaluation Supporting Util Decommissioning Funding Assurance Plan for Facility Per Commission Decision 88-10 ML20245J0751989-04-25025 April 1989 Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20246N8731989-03-21021 March 1989 Safety Evaluation Accepting Util 881118 Submittal on Isolation Devices ML20205Q5721988-10-31031 October 1988 SER Re Const Mod & Licensing of Company Facility-1 Cpdf. Licensee Technically Qualified to Modify Existing Facility in Such Way as to Assure Adequate Protection of Common Defense & Security ML20205Q5761988-10-31031 October 1988 SER Re Application for CP for Alchemie Facility-2 Oliver Springs.Licensee Technically Qualified to Construct & Operate Proposed Facility in Such Way as to Assure Adequate Protection for Common Defense & Security ML20205M5731988-10-26026 October 1988 Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20155G4801988-09-28028 September 1988 Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively ML20154Q9881988-09-27027 September 1988 Safety Evaluation Supporting Amend 1 to License NPF-56 ML20153D2321988-08-24024 August 1988 Safety Evaluation Accepting Licenseee Proposed Mod to Control Room Habitability Sys ML20195G5531988-06-24024 June 1988 Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pools from Criticality Standpoint.Enrichment of Fuel to 4.5 Weight % U-235 May Be in Conflict W/ 10CFR51 Table S4 & Should Be Investigated by NRC ML20154H2171988-05-18018 May 1988 Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program ML20147D9631988-02-25025 February 1988 Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90 ML20147E9261988-02-23023 February 1988 Safety Evaluation Supporting Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively ML20236M9631987-11-0606 November 1987 Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue ML20236L2001987-10-30030 October 1987 Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72 ML20195G5501987-10-28028 October 1987 Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pool.Licensee May Be Required to Perform Addl Analyses to Verify Maint of Required Subcriticality If Staff Boraflex Studies Reveal Gap Development in Subj Boraflex ML20235G9651987-09-24024 September 1987 SER Re Setpoint Methodology for Rosemont Replacement Transmitters.Licensee Proposed Methodology Not Adequate to Allow Approval to Be Used in Application of Units ML20235A7331987-09-18018 September 1987 Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable ML20195G5461987-08-21021 August 1987 Safety Evaluation Accepting Proposed Util Tech Specs Change to Increase Max Allowed Enrichment of Reload Fuel to 4.2 Weight % U-235 ML20236Y0221987-07-0808 July 1987 Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant ML20214M3361987-05-22022 May 1987 Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing ML20214M1491987-05-21021 May 1987 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 2) Re Established Interface W/Nsss or Vendors of Each Component of Reactor Trip Sys ML20153F3851987-05-0404 May 1987 SER Accepting Util 870301 & 0407 Requests for Rev to Tech Specs,Modifying MSIV Actuation Control Sys,Per IEEE Std 279 & GDC 21 ML20153F3671987-04-30030 April 1987 Safety Evaluation Accepting Util 870311 Proposed Changes to Tech Spec Tables 2.2.1-1,3.6.1.2-1 & 3.6.3-1 Re MSIV-closure Setpoint ML20207R6481987-03-11011 March 1987 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification.Program Acceptable ML20212J4041987-03-0202 March 1987 Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Licensee Meets NRC Position ML20212B5671987-02-24024 February 1987 Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Reliability On-Line Testing. Response Acceptable ML20211Q2971987-02-18018 February 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2 ML20211G4361987-02-14014 February 1987 Safety Evaluation Supporting Util 831110 Response to Generic Ltr 83-28,Item 4.5.2 Re on-line Testing for Reactor Trip Sys Reliability ML20153F3511987-02-0707 February 1987 Safety Evaluation Accepting Util Latest Design Mods to MSIV Actuation Control Sys,Per IEEE 279 & GDC 21 ML20210R2061987-02-0606 February 1987 Safety Evaluation Supporting Util 850517,0802,0823,1211 & 860429 Submittals Re Environ Effects of High Energy Line Breaks in Auxiliary Steam or Steam Generator Blowdown Sys. Design of Blowdown Sys Acceptable ML20210T2571987-02-0606 February 1987 SER Re Util 850802 Submittal Describing Design Details of Steam Generator Blowdown & Auxiliary Steam Sys to Detect & Isolate High Energy Line Breaks.Sys Design Acceptable, However,Two Deviations from IEEE-STD-297 Criteria Apparent ML20209B1511987-01-28028 January 1987 SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing ML20209C3571987-01-23023 January 1987 SER Supporting Facility Design,Per Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing ML20209C2151987-01-21021 January 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) at Prairie Island Units 1 & 2.Util Actively Pursuing Improvements in Sys Reliability & Reducing Sys Challenges 1999-09-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H2841999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Seabrook Station. with ML20212D1461999-09-17017 September 1999 SER Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20212B8671999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Seabrook Station. with ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20210Q7581999-08-11011 August 1999 SER Approving Proposed Merger of CES & Bec,Which Will Create New Parent Company of Canal ML20210R9781999-08-0606 August 1999 ISI Exam Rept of Seabrook Station, for RFO 6,period 3 ML20210J8681999-08-0303 August 1999 SER Approving License Transfer from Montaup Electric Co to Little Bay Power Corp & Approval of Conforming Amend for Seabrook Station Unit 1 ML20210R6001999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Seabrook Station, Unit 1.With ML20209H1371999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Seabrook Station, Unit 1.With ML20210H1151999-06-30030 June 1999 Naesc Semi-Annual Fitness-for-Duty Rept for 990101-0630 ML20195G5391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Seabrook Station, Unit 1.With ML20195C0491999-05-25025 May 1999 Offshore Intake Seal Deterrent Barrier Design ML20206N1751999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Seabrook Station, Unit 1.With ML20206E4761999-04-30030 April 1999 LER 99-S01-00:on 990408,contractor Employee Was Granted Temporary Unescorted Access to Seabrook Station Protected Area.Caused by Failure of Contractor Employee to Provide Accurate Info.Individual Access Revoked.With ML20196L2081999-04-19019 April 1999 Rev 01-07-00 to RE-21, Cycle 7 Colr ML20205K5441999-03-31031 March 1999 Decommissioning Update ML20205L8141999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Seabrook Station. with ML20205C1981999-03-24024 March 1999 Safety Evaluation Concluding That Proposed Relief Request IR-8,Rev 1,provides Acceptable Alternative to ASME Code Requirements.Recommends Authorization of Proposed Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20207F4941999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Seabrook Station. with ML20202E8241998-12-31031 December 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980701-981231 ML20198P1831998-12-31031 December 1998 LER 98-S01-00:on 981214,incomplete pre-employment Screening Records Was Noted.Caused by Failure of Contractor Employee to Provide Accurate Info.Subject Contractor Employees Employment Was Terminated.With ML20199E6731998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Seabrook Station, Unit 1.With ML20196F5741998-12-0202 December 1998 Safety Evaluation Concluding That Licensee Has Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Seabrook ML20198B8661998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Seabrook Station, Unit 1.With ML20195D0311998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Seabrook Station, Unit 1.With ML20154H5291998-10-0808 October 1998 Special Rept:On 980928,meteorological Monitoring Instrumentation Channel Inoperable for Period Greater than 7 Days.Caused by Vendor to Follow Std Industry Practice for Calibr of Instrumentation.Instruments Installed ML20154M8421998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Seabrook Generating Station,Unit 1.With ML20151V5951998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Seabrook Station, Unit 1.With ML20237B4501998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Seabrook Station ML20236R1781998-06-30030 June 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980101-0630 ML20236M3591998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Seabrook Station, Unit 1 ML20237A4871998-06-0303 June 1998 North Atlantic Seabrook Station 1998 Exercise on 980603 ML20248M2951998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Seabrook Station, Unit 1 ML20247G2641998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Seabrook Station ML20247H3171998-04-27027 April 1998 Rev 1 to Seabrook Station SGs B & C Isi,May/June 1997 ML20216F8891998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Seabrook Station 05000443/LER-1998-002, Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted1998-03-20020 March 1998 Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted ML20216H9211998-03-13013 March 1998 Fitness for Duty Program Performance Data Personnel Subject to 10CFR26 ML20248L2811998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Seabrook Station, Unit 1 ML20197A7531998-02-27027 February 1998 Safety Evaluation Accepting License Request for Relief from ASME Code,Section IX Requirements Re Inservice Insp of RHR Heat Exchanger Nozzle Welds & Reactor Vessel Closure Head Nuts ML20202G3701998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Seabrook Station ML20198G1021997-12-31031 December 1997 Baycorp Holdings 1997 Annual Rept ML20203G9881997-12-31031 December 1997 Naesc Semi-Annual Fitness-for-Duty Rept for Jul-Dec 1997 ML20248L7711997-12-31031 December 1997 Western Massachusetts Electric 1997 Annual Rept. Supporting Info,Encl ML20198F9511997-12-31031 December 1997 United Illuminating Co 1997 Annual Rept ML20198G0351997-12-31031 December 1997 Eastern Edison Co 1997 Annual Rept ML20198G0121997-12-31031 December 1997 New England Power Co 1997 Annual Rept ML20198G0271997-12-31031 December 1997 Commonwealth Energy Sys 1997 Annual Rept ML20198G0681997-12-31031 December 1997 Taunton Municipal Lighting Plant 1997 Annual Rept ML20198G0481997-12-31031 December 1997 New Hampshire Electric Cooperative 1997 Annual Rept 1999-09-30
[Table view] |
Text
1 SAFETY EVALUATION REPORT SEABROOK STATION, UNIT N05. I AND 2 DOCKET N05. 50-443/444 .
CONFORMANCE TO REGULATORY GUIDE 1.97 INTRODUCTION AND
SUMMARY
Public Service of New Hampshire was requested by Generic Letter 82-33 to provide . 1
- a. report-.to the NRC describing ~ how the post-accident monitoring instrumentation - q a
meets the guidelines of Regulatory Guide 1.97 as applied to emergency response- 1 facilities' . The applicant's response to Regulatory Guide 1.97 was provided by letter dated August 30, 1985 and' Revision 58 of the FSAR.
1 A detailed review and technical evaluation of the. licensee's submittals was perfonned by EG8G Idaho,'Inc.,'under contract' to the NRC, with general Jsuper-vision by the NRC staff. This work was reported by.EG&G in the Technical :)q Evaluation Report (TER)', "Confonnance to Regulatory Guide -1.97, Seabrook Station, i Unit Nos. I and 2," dated May 1986 (attached). We have reviewed this report and concur with the conclusion that the licensee either conforms to, or has ade- 1 1
quately justified deviations from, the guidance of Regulatory Guide:1.97 for.- j each post-accident monitoring variable except for the variables accumulator tank level and pressure, quench tank temperature, and containment sump water temperature.
EVALUATION CRITERIA Subsequent to the issuance of the generic letter, the.NRC held regional meet--
ings in February and March 1983 to answer licensee and applicant questions-'and--
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concerns regarding the NRC-policy on Regulatory Guide 1.97.: fat these meetings. !
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it was established that'the NRC review would only address exceptions'taken'to; the guidance of. Regulatory Guide > 1.97. Further, where licensees-or applicants -
8706230147 870618 d PDR FOIA e
.CONNOR87-213 PDRg. .
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explicitly state that instrument systems confonn to the provisions of the regulatory guide, no staff review would be necessary for those items. There-fore, the review perfonned and reported by EG&G only addresses exceptions tp ;
the guidance of Regulatory Guide 1.97. This Safety Evaluation addresses the i l
licensee's submittals based on the review policy described in the NRC regional l meetings and the conclusions of the review as reported by EG&G.
EVALUATION l We have reviewed the evaluation performed by EG&G contained in the enclosed l
i TER and concur with its bases and findings. The licensee either. conforms to, or has acceptably justified deviations from, the guidance of Regulatory Guide 1.97 for each post-accident monitoring variable except for accumulator tank
)
level and pressure, quench tank temperature, and containment sump water temperature. .!
For the variable boric acid charging flow addressed in section 3.3.2.5 of the EG&G TER, Revision 58 of the Seabrook FSAR provided a justification for its classification as a Design Category 3 variable as opposed to Design Category 2 in Regulatory Guide 1.97. This justification was not available to EG&G at the time they were conducting their review of this item. The justification states that emergency boration is not required in the mitigation of design basis accidents. The RWST provides the required volume of borated water for all design basis accidents. - Emergency boration may be used to assist-in the
recovery if available. Therefore, the monitoring of emergency boration flow'is classified as Design Category 3.
Because emergency boration flow is not a safety injection flow at this station, we find that classification of this variable as Design Category 3 is acceptable.
With regard to pressurizer heater status addressed in section 3.3.10 of the EG&G,TER, the applicant, in a letter dated May 30, 1986 provided a rev.ision to Table 7.5-1 which now indicates that this variable is categorized as Design Category 2. This is in accordance with the recommendations of R.G. 1.97 and I is therefore acceptable. '
With regard to the variable accumulator tank level and pressure addressed in section 3.3.7 of the EG8G TER, the applicant has provided a letter dated j l
June 6,1986 which commits to install an environmentally qualified accumulator j tank level or pressure instrument which meets the requirements for a Category 2 -
instrument contained in R.G. 1.97. Likewise the letter comits to install an )i environmentally qualified containment sump water temperature instrument which '
meets the Category 2 R.G.1.97 requirements. Containment sump water temperature 1
is addressed in section 3.3.17 of the EG&G report. The_ applicant commits to install these instruments prior to startup following the first refueling outage.
We find these commitments acceptable. ;
1 1
1 With regard to the. Quench Tank (Pressurizer Relief Tank) Temperature addressed 1
in section 3.3.11 of the EG&G TER, the applicant is supplying a temperature I
.l range of 50-250*F which deviates from the recommended. range of 50-750*F. His !
1 justification is that the Pressurizer Relief-Tank (PRT) temperature measurement ]
is used in' conjunction with PRT level and pressure indication to determine if PRT conditions are " normal." He states that the temperature range provided is i
sufficient to indicate a change from normal ~ operating conditions, and fully i enveloping the. expected temperature to be encountered is not necessary in this case, l l
The applicant's justification is not acceptable. The applicant should show that the temperature indication will remain functional and on-scale, including the maximum expected saturation temperature, during any accident that lifts the-
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pressurizer relief valves, or provide a range that will envelop these conditions.
i CONCLUSION l
Based on the staff's review of the enclosed Technical Evaluation Report and the
{
applicant's submittals, we find that the Seabrook Station, Unit Nos.'I and 2 j design is acceptable with respect to conformance to Regulatory Guide 1.97, .
Revision 3 except-for the accumulator tank level and pressure instrumentation, containment sump water temperature instrumentation, and quench tank temperature' instrumentation.
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1
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The applicant's~ commitment to install a category 2 accumulator tank level or pressure instrument and a category 2 containment sump water temperature in-strument prior to startup from the first. refueling outage will bring the , ,
design of these. instruments into conformance with R.G. 1.97. We therefore find this comitment acceptable. . )
I For the quench tank temperature indication the applicant should show that the -
temperature indication will remain functional and on-scale, including the ' ,
maximum expected saturation temperature, during any accident that lifts the l
pressurizer relief valves, or provide a range that will envelop these conditions. ;
)
If an expanded range is necessary it should be installed before startup from the '
first refueling outage. ,
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