|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant ML20153B5611998-09-0101 September 1998 Rev 1 to JAF-SE-98-013, RHR & Core Spray Suppression Pool Suction Strainer Replacement ML20153B5781998-07-28028 July 1998 Rev 0 to JAF-SE-98-025, HPCI & RCIC Suppression Pool Suction Strainer Replacement ML20236X3831998-07-14014 July 1998 Rev 2 to JAF-RPT-MULTI-02671, Summary of Detailed Evaluation for NRC Generic Ltr 96-06 ML20202G9081998-02-0606 February 1998 Safety Evaluation Re Amend to License DPR-59 to Revise TS Tables 3.2-2 & 4.2-2 ML20236V8301998-01-31031 January 1998 Review & Evaluation of Historical Fire Protection Licensing Basis Related to Fire Areas Ix,X,Xi,Xv,Xvii & Xviii at Ja FitzPatrick Nuclear Power Plant ML20211H0861997-09-26026 September 1997 Safety Evaluation for Proposed TS Changes to ASME Section XI Surveillance Testing ML20217J0091997-07-21021 July 1997 Rev 4 to JAF-RPT-DHR-02413, Evaluation of Decay Heat Removal Sys ML20217J0181997-07-18018 July 1997 Non-proprietary Version of Rev 3 to Licensing Rept for Reracking of Ja FitzPatrick Spent Fuel Pool ML20135E3771996-11-30030 November 1996 Evaluation of Ultrasonic Indications in RPV Closure Head Weld VC-TH-1-2 at James a Fitzpatrick Nuclear Power Plant ML20129F9001996-07-18018 July 1996 Nonproprietary Ja FitzPatrick Nuclear Power Plant ATWS Analysis for Recirculation Pump Trip (RPT) Setpoint Changes ML20116D8981996-07-16016 July 1996 Installation & Acceptance Testing of Dhrs ML20116D8921996-07-16016 July 1996 Evaluation of Dhrs ML20116D9021996-07-16016 July 1996 Use of Dhrs in Various Plant Modes & Configurations ML20094M0591995-09-30030 September 1995 Ja FitzPatrick Nuclear Power Plant USI A-46 Seismic Evaluation Rept ML20094M0481995-09-30030 September 1995 Ja FitzPatrick Nuclear Power Plant Safe Shutdown Equipment & Relay Evaluation for USI A-46 ML20094M0391995-09-30030 September 1995 Ja FitzPatrick Nuclear Power Plant USI A-46 Project Summary ML20094B6781995-09-0101 September 1995 Containment Sys Surveillance Test Extensions, for Ja Fitzpatrick-24 Month Operating Cycle ML20094R7001995-08-18018 August 1995 SLC Surveillance Extensions ML20087K7431995-05-31031 May 1995 Jaf - 24 Month Operating Cycle Nuclear Steam Supply Sys Surveillance Test Improvements ML20081K0791995-03-31031 March 1995 Ja FitzPatrick Nuclear Power Plant Core Shroud Vertical & Top Guide Support Ring Radial Weld Flaw Evaluation Screening Criteria ML20080P9761995-02-28028 February 1995 Response to NUREG-0737,III.D.3.4 CR Habitability for Jafnpp ML20081K0691994-12-20020 December 1994 Nonproprietary Version of Cert Testing of Type XM-19 in Simulated BWR Environ ML20077A2631994-11-30030 November 1994 Response to NUREG-0737,III.D.3.4,Control Room Habitability for Ja FitzPatrick Nuclear Power Plant ML20077A5591994-11-16016 November 1994 Nonproprietary Ja FitzPatrick Cycle 12 ATRIUM-10A Lead Fuel Assembly Licensing Evaluation ML20077A5631994-11-16016 November 1994 Nonproprietary Ja FitzPatrick ATRIUM-10A Design Description ML20080B9441994-10-27027 October 1994 Shroud Safety Assessment ML20076H3871994-10-11011 October 1994 Shroud Safety Assessment ML20092H5591994-09-20020 September 1994 24 Month Operating Cycle Auxiliary Electrical Sys Surveillance Test Extensions ML20072K7171994-08-22022 August 1994 Probabilistic Risk Assessment of Effects of Postulated Events w/360 Degree Shroud Through-Wall Crack ML17059A3611994-07-0606 July 1994 Emergency Action Level Verification & Validation Rept. ML20087K7471994-06-27027 June 1994 24 Month Operating Cycle Svc Water Sys Surveillance Test Improvements ML17311A0181994-05-13013 May 1994 New York State EAL Upgrade Project Verification & Validation Rept. ML20247F9711994-04-30030 April 1994 Rept EP 91-28, Eastern Lake Ontario On-Shore Flow Field Study ML20126H4751992-12-22022 December 1992 Rev 0 to Alternate Electrical Separation Criteria ML20126H4721992-12-22022 December 1992 Rev 0 to Evaluation of Apparent Electrical Separation Anomalies ML20115J3871992-10-26026 October 1992 Safe Shutdown Capability Reassessment,10CFR50,App R ML20087K7261992-07-21021 July 1992 Jaf - 24 Month Operating Cycle Shock Suppressors (Snubbers) Surveillance & Maint Extensions ML20086T5781991-12-16016 December 1991 Results Improvement Program ML20086U0211991-11-26026 November 1991 Vols 1 & 2 of Qualification of Inconel 82 Temperbead Weld Overlay Repair W/Reduced Preheat & No Post Weld Heating W/Appendices ML20087K7551991-11-12012 November 1991 24 Month Operating Cycle CRD Surveillance Test Extensions ML20087A0291991-10-0909 October 1991 Rev 1 to Ja Fitzpatrick Nuclear Power Plant Evaluation of Suppression Chamber & Main Steam Safety Relief Lines for Simultaneous Actuation of All Safety Relief Valves Set at 1,145 Psig ML20091C2471991-07-30030 July 1991 Engineering Assessment Turbine Bldg Fire Area Ie,Ja Fitzpatrick Nuclear Power Plant ML20091C2571991-07-30030 July 1991 Engineering Assessment Battery Room Corridor,Ja Fitzpatrick Nuclear Power Plant ML20076C4191991-07-12012 July 1991 Suppl a to Holtec Rept HI-89399 Re Mod to Util Application for Storage Capacity Expansion of Spent Fuel Pool to Incorporate Dimensional Changes in Module Layout ML20247F9481991-06-30030 June 1991 Final Task Rept Review of Formulas & Observation of Thermal Internal Boundary Layers in Shoreline Environments ML20247F9101990-12-31031 December 1990 Final Task Rept Fumigation Frequency Analysis:Nine Mile Point Mile Point Nuclear Power Station,Lycoming,Ny 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARJAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Jafnpp.With JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with ML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with1999-06-0202 June 1999 Annual Summary of Changes,Tests & Experiments for 1997/1998. with JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Jafnpp.With JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20198F9991998-12-0404 December 1998 Assessment of Licensing Basis for Use of Containment Overpressure Credit for Net Positive Suction Head Analyses Power Authority of State of New York,James a Fitzpatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195J7521998-11-18018 November 1998 Rev 7 to Jaf Colr ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20153B5611998-09-0101 September 1998 Rev 1 to JAF-SE-98-013, RHR & Core Spray Suppression Pool Suction Strainer Replacement ML20151X6891998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Ja FitzPatrick Nuclear Power Plant ML20237E8361998-08-25025 August 1998 Rev 6 to Colr ML20237E9471998-08-0808 August 1998 Rev 6 to Colr JAFP-98-0264, Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20153B5781998-07-28028 July 1998 Rev 0 to JAF-SE-98-025, HPCI & RCIC Suppression Pool Suction Strainer Replacement ML20236X3831998-07-14014 July 1998 Rev 2 to JAF-RPT-MULTI-02671, Summary of Detailed Evaluation for NRC Generic Ltr 96-06 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant JAFP-98-0222, Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0193, Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant1998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0128, Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively JAFP-98-0091, Monthly Operating Rept for Feb 1998 for JAFNPP1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for JAFNPP ML20202G9081998-02-0606 February 1998 Safety Evaluation Re Amend to License DPR-59 to Revise TS Tables 3.2-2 & 4.2-2 JAFP-98-0058, Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant 1999-09-30
[Table view] |
Text
. _ _ . . . . .
_ . ,. . . . . - _ . . . . _ .. . . _ _ _ . ~ _ _ . - ~ - . _ . . .
. ~ i. . ; ,,
~
ATTACHMENT.II t
\
Power Authority of the State of New York J. A. FitzPatrick Nuclear Power Station ACTION PLAN FOR THE IMPLEMENTATION OF SECTION III.G. .
" FIRE PROTECTION OF SAFE SHUTDOWN CAPABILITY" OF APPENDIX R TO 10CFR50.
June 22, 1981 i
a
{- .
8106300 %%-
'I o. .
ATTACHMENT II INTRODUCTION On February 17, 1981, Section 10CFR50.48 and Appendix R to 10CFR50 became effective.. Section 10CFR50.48 requires that all operating reactors licensed to operate prior to January 1, 1979 meet the requirements of Section III.G, III.J and III.O of Appendix R. This section also requires that plans and schedules and/or exemption requests for meeting the fire protection requirements in these sections be submitted not later than March 19, 1981.
Section III.O applies to plants ~which do not have an inerted containment. Therefore, this Section is not applicable to the FitzPatrick facility since its containment is inerted. In the Authority's consideration, Section 10CFR50.48 did not allow sufficient time to perform the appropriate evaluation and prepare plans and schedules to implement the requirements of Section III.G
. and III.J. Accordingly, additional time was requested to submit this information on December 28, 1981 and June 22, 1981, respectively. In addition, the Authority committed to prepare and submit to the NRC, on June 22, 1981, an action plan which would show the systematic evaluation required for the preparation of plans and schedules in order to meet.the requirements of Section III.G. This action plan is presented below. Plans and schedule for Section III.J are provided in a separate report eatitled " Appendix I to Safe Shutdown Analysis Response to 10CFR50 Appendix R Fire Protection Section III.J, " Emergency Lighting". .
PURPOSE The purpose of the action plan is to provide a method to system-atically evaluate the requirements of Section III.G. Appendix R to 10CFR50 as applicable to the FitzPatrick Facility and identify the required plant modifications or actions. This action plan provides a means to utilize the resources available .in an optimum manner to implement'these fire protection requirements in a timely fashion.*
This action plan identifies and provides a detailed schedule for each of the aspects associated with meeting the requi ements of Section III.G.
ACTION PLAN Prior to determining which of the options provided in Section III.G will be satisfactory for the FitzPatrick facility, a comprehensive analysis must be performed for safety-related circuits and assoc-iated non-safety related circuits of each fire zone. This analysis will identify the critical circuits, equipment, and fire zones and will assess the potentially adverse impact the loss of each may have on the plant's ability to achieve and maintain safe shutdown conforming to the criteria of Section III.G.
- It should be noted that the Authority is concurrently engaged in the implementation of various other major modifications, e.g., TMI; !
Mark I, CRD System, RPS System, IEB 79-OlB, etc.
1-I l
.- . j l
l I
The Authority has completed an extensive review of the safety related circu.its; a1similar review of non-safety related associated circuits is currently underway.. Additionally, a reexamination of the safety related cables in accordance with the Appendix R requirements and the-staff's feedback on the Authority's previous submittals in also being performed. These efforts are detailed in the' attached figure. Each step in the figure relating to Section III.G is further explained below.
IV. l.- Review of All Non-Safety CablesSection III.G requires in part that cables including non-aafety associated circuits that could prevent operation or cause maloperation due to hot shorts, open circuits or-short to ground of the alternative train which is used to, or redundant trains of systems necessary to achieve and maintain hot shutdown conditions are located within the same fire area outside the primary containment be provided with one of the methods outlined in paragraphs III.G.2.a, III.G.2.b or III.G.2.c. Thus, cables including non-safety cables which fall under the above criteria need to be identified. This tedious effort requires that each and every cable in the Plant be reviewed and numerous computer runs be performed in order to single out the subject cables. This effort requires approximately 23 weeks to be
. completed.
IV. 2. Engineering Evaluation -
- As the affected cables are identified, the following -
criteria of Section III.G. are applied:
a) Separation by a fire barrier having a 3-hour rating; b) Separation by a horizontal distance of 20 feet; c) Enclosure in a fire barrier having a 1-hour rating along with fire detection and automatic suppression equipment.
Additionally, those cables or systems which do not comply with the above criteria must be further evaluated to determine and demonstrate equivalent protection. For those cases in which equivalent protection can be demonstrated, appropriate safety evaluations and documentation must be prepared in order to support future exemption requests.
This effort requires input from 1. above. However, this effort was started as soon as practicable and is being performed parallel to Step 1. This effort requires approximately 23 weeks for completion and is constrained by the completion of 1. above.
8
e ,J
_ IV. 3. Review Impact on Systems ,
As efforts 1. and 2. above are completed, those cases which
~
do not comply with Appendix R are identified for each fire zone.- This requires additional analyses to determine the impact on the alternative or redundant safe shutdown equipment in the event of a' postulated fire. Should this
~
analysis indicate that the cable or system is impottsnt to safe shutdown, further analysis performed to determine alternate means for. safe shutdown or a plant modification is identified. .This effort requires approximately 19 weeks for completion and is constrained by 1. and 2. above. Since.a.
good portion of items 1. and 2. needs to be completed, this effort was started later.
IV. 4. Determination of the-Modifications or Exemptions Upon completion of efforts 1. through 3. above, those areas which may require a modification to comply with Appendix R requirements are identified. Once again, for these areas, the criteria of paragraph III.G.2.a. , b., and c. are applied. An evaluation i's performed to demonstrate which is the optimum method of compliance and either exemptions or modifications are determined. This analysis takes into consideration, such aspects as safety significance of the modification and installation requirements, e.g., outage requirements and length and practicality of installations.
This effort requires approximately 13 weeks to be completed and is constrained by efforts 1. through 3. above. This ef fort could not be started until a good portion of the data from the previous efforts was available.
IV. 5. Report Preparation An additional 14 weeks are necessary for the preparation of a report in order to fully document the result of the reexamination. This time is necessary for the preparation of the report, in-house reviews, and publication. Also, additional effort is required to determine the schedule for-the plant modification identified.
Reevaluation of Safety Cablec l IV. 6.
The Authority has previously submitted a safe shutdown analysis and a fire hazard analysis in accordance with BTP APCSB-9.5-1. Those documents ensured that a shutdown capability with respect to safety systems is provided.
However, a re-analysis in this area is necessary based on Appendix R requirements and the' interim report received from the NRC staff (NRC letter, T. P. Ippolito to G.T. Berry dated April 21, 1981). Much work has been performed in this subject; however, efforts similar to 1. through 5. above are necessary for those areas of concern.
.e .
1 Section III.G requirements are applicable to cables for systems necessary to achieve and maintain hot shutdown. Nevertheless, rather'thanLdemonstrate that the cold-hutdown system can'be repaired within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> at-this time, the Authority has-decided to perform the evaluation of all' cables. including those required to achieve and maintain cold shutdown. Thus, the number of cables to be. evaluated
- was greatly increased.
4 1
. G
. ;
I e
i J
k 4
l 4
1 , , - , -- ,,--.v- -
SCHEDULE FOR 10 CFR 50.43 AND APPENDIX R. REQUIREMENTS seso i:ss lee NOV DEC JAN FE8 MAR APR MAY JUN , JUL , AUG , SEP , OCT NOV DEC ,
L EV ALU ATION OF t 1/ 2 4 3182 to CFR 60.48 C O .
AND APPENOlX R REOUIREMENTS NEGOTBATIONS WITH ARCNITECT ENGINEER 3112 1922 II. ACTlON PLAN lie O PREPARATION C O lat. EVALUATION OF APPENDIX R SECTiON til J 4/10 7/23 AND PREPARATION OF PLANS AND SCHEDULE C O IV. ACTION PLAN FOR SECTION 185 O. APPENDIX R.
3112 S121
- 1. REVIEW ALL NON-SAFETY CASLES g 9 3/27 9/4
- 2. ENGINEERING REVlEW ___C 3 4/24 ese B. REVIEW IMPACT .aSYSTEMS -------C O esse este
- 4. DETERMINE TYPE MODIFIC ATION _---------.C O OR EXEMPTIONS 974 10/30 12ft1 S. REPORT PREPARATION _--------------------C O O i \ 1.. .... . .. .l..
Final pubNcation g
3/12
- 6. RE-EX AMINATION OF SAFETY CABLES _4 6 ella
--- -- _ - .