Text

Status of Safety Issues at Licensed Power Plants.Tmi Action Plan Requirements,Unresolved Safety Issues,Generic Safety Issues,Other Multiplant Action Issues
	ML20078J768
Person / Time
Issue date:	12/31/1994
From:	; Office of Nuclear Reactor Regulation
To:	;
References
	REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR, TASK-TM NUREG-1435, NUREG-1435-S04, NUREG-1435-S4, NUDOCS 9502080207
	Download: ML20078J768 (157)
	v • d • e

{{#Wiki_filter:.- a NUREG-1435 Supplement 4 Status of Safety Issues at Licensed Power Plants i TMI Action Plan Requirements Unresolved Safety Issues j Generic Safety Issues Other Multiplant Action hsues U.S. Nuclear Regulatory Commission O!Tice of Nuclear Reactor Regulation 4 ) 4 %,...../

M2 AMN "'" '

1435 R PDR

AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources: 1. The NRC Putlic Docurnent Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents U.S. Government Printing Office, P. O. Box 37082, Washington, DC 20402-9328 3. The Natior.al Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustivo. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room includo NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information noticos, inspection and investOation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu-monts and correspondence. The following documents in the NUREG series are available f or purchese from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro-ceedings, international agreement reports, granteo reports, and NRC booklets and bro-chures. Also available are regulatory guides, NRC regulations in the Code of Fedoral Regula-tions, and Naclear Regulatory Commission Issuances. Documents available from the National Technical Information Servico include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, Journal articles, and transactions. Federal red / ster notices, Federal anc Stato legislation, and congrossional reports can usually be obtained from these libraries. Documents such as theses, dissertations, foreign reports and translations, and non-NRC con-forence proceedings are available for purchase from the organization sponsoring the publica-tion ci!cd. Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. Copies of industry codes and standards used in a substantivo manner in the NRC regulatory process are maintained at the NRC Library, Two White Flint North,11545 Rockville Pike, Rock-ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards Institute,1430 Broadway, New York, NY 10018-3308.

NUREG-1435 Supplement 4 Status of Safety Issues at Licensed Power Plants TMI Action Plan Requirements Unresolved Safety Issues Generic Safety Issues Other Multiplant Action Issues Manuscript Completed: November 1994 Date Published: December 1994 Omce of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 p** ** *%, W.....)

l \\ l ABSTRACT As part of ongoing U.S. Nuclear Regulatory Coinmission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a { program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSis). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30,1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30,1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSis. Supplement 3 gives status as of September 30, 1993. This annual report, Supplement 4, presents updated information as of September 30,1994. The agency has put-in-place several initiatives with the intention of reducing the number of administrative non-safety relevant requirements contained in licensing documents such as technical specifications. Because of the non-safety relevance of these items, the application for removal of these items from the license has been left to the option of the licensee. For purposes of completeness, these items were reported last year in Supplement 3 of NUREG-1435. However, because of the lack of safety relevance, these items are not being reported in this supplement. Supplement 3 provided updated information for 109 plants as of September 30, 1993. This report, Supplement 4, provides data for 107 plants in order to directly focus attention on operating plants, this report excludes Browns Ferry 1 and Browns Ferry 3 which have been indefinitely shutdown since 1985. In 1993 the licensee declared the plants to have a Maximum Dependable Capacity (MDC) of zero, retroactive to June 1,1985. When these plants become active, the NRC will report thc status of all remaining open safety issues. The data contained in this supplement is produced using the NRC's safety issues management system (SIMS) database, which is maintained by the project management staff in the Office of Nuclear Reactor Regulation and by the staff in NRC's regions. This report gives a comprehensive description of the implernentation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSis, and other MPAs that have been resolved and involve irnplementation of I an action or actions by licensees. This report makes the information available to lii-

I other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, "A Prioritization of Generic Safety issues," which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees. i I s s 4 s h ? L l 1 i j t [ t i I l l t --IV-

.~ CONTENTS A BSTR A CT............................................... iii EXECUTIVE SUMM ARY....................................... vii A BBR EVI ATI O N S........................................... xi e 1 I NTRO D U CTI O N...................................... 1 1.1 Background................................ 2 1.2 Process and Accountability....................... 3 1.3 De finitio ns.................................. 5 l 2 THREE MILE ISLAND ACTION PLAN REQUIREMENTS 7 2.1 Implementation Status..... -..................... 7 3 H 2.2 Verification Status............................ 11 2.3 Status by Plant.............................. 13 2.4 Status by lssue...,.......................... 17 2.5 Co nclu sio n s................................ 31 3 UNRESOLVED S AFETY ISSUES............................ 33 3.1 Implementation Status..................,...... 33 1 3.2 Verification Status............................ 38 3.3 Stat us by Pla nt.............................. 41 3.4 Status by issue............................. 45 3.5 Conclusions................................ 49 4 GENERIC SAFETY ISSUES............................... 51 4.1 Implementation Status......................... 51 4.2 Verification Status............................ 58 4.3 Status by Pla nt.............................. 61 4.4 Status by issue.............................. 6 5 4.5 Conclusions............................... 69 5 OTHER MULTIPLANT ACTION ISSUES....................... 71 5.1 Implementation Status......................... 71 5.2 Verification Status............................ 86 i 5.3 Status by Plant.............................. 89 5.4 Status by issue............................. 93 5.5 Co nclusio n s............................... 10 5 -v-l

APPENDICES A Listing of Unimplemented TMl items by issue ...............A-1 B Listing of Unimplemented USl items by issue................ B-1 C Listing of Unimplemented GSI Items by issue................ C-1 D Listing of Other Unimplemented MPA Items by Issue ..........D-1 FIGURES 2.1 TMl Action Plan Requirements - Implementation Status at Licensed Plants 8 2.2 Projected Schedules for Remaining TMI Items 9 3.1 Unresolved Safety issues - Implementation Status at Licensed P la n t s....................................... 3 4 3.2 Summary of Three Unimplemented USIs............... 36 4.1 Generic Safety issues - implementation Status at Licensed P la n t s....................................... 5 3 4.2 Summary of Five Unimplemented GSis................ 55 5.1 Other MPA issues - Implementation Status at Licensed Plants. 75 5.2 Summary of Sixteen Unimplemented MPAs............. 76 TABLES 2.1 Summary of the Remaining TMl items by Area........... 10 2.2 Summary of the Remaining TMI Items by Plant.......... 12 2.3 Status of TMI Action Plan - Summary by Unit........... 14 2.4 Status of TMI Action Plan - Summary by item........... 18 3.1 Summary of Unimplemented USl items by Plant.......... 35 3.2 Summary of USl items Requiring Verification........,,.. 39 3.3 Status of USis - Summary by Unit ..................,.42 3.4 Status of USIs - Summary by item................... ~46 4.1 GSI Numbers and Corresponding SIMS Item Numbers....... :52 l 4.2 Summary of Unimplemented GSI Items by Plant.........,, 54 1 4.3 Temporary instructions for Resolved GSis.......,.....,. 59 4.4 Summary of <GSI Items Requiring Verification............ 60 4.5 Status of GSis - Summary by Unit................... 62 4.6 Status of GSis - Summary by item................... 66 5.1 SIMS lssue Numbers and Corresponding MPA Number..... 72 ) 5.2 Summary of Unimplemented MPA Items by Unit.......... 74 5.3 Temporary Instructions for Resolved MPAs............. 87 I 5.4 Summary of Other MPA Items Requiring Verification....... 88 5.5 Status of Other MPAs - Summary by Unit.............. 90 5.6 Status of Other MPAs - Summary by item.............. 94 -vi-

EXECUTIVE

SUMMARY

This U.S. Nuclear Regulatory Commission (NRC) report covers the implementation and verification status of the Three Mile Island (TMI) Action Plan requirements, unresolved safety issues (USIs), generic safety issues (GSis), and other multiplant action (MPA) issues not related to TMl Action Plan requirements, USIs, or GSis at 107 licensed nuclear power plants. The implementation and verification status are current as of September 30,1994. Backaround The implementation and verification status of TMI Action Plan requirements, USIs, and GSis was initially reported in Volumes 1, 2, and 3 of NUREG-1435, published in 1991. The first annual supplement consolidated and updated the information given in the earlier three volumes; it was published in December 1991 and provided updated information as of September 30,1991. The second supplement was published in December 1992 and gave updated lnformation as of September 30,1992. Supplement 2 also gave the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMl Action Plan requirements, USis, or GSis. Supplement 3 gave updated information as of September 30,1993. This annual report, Supplement 4, presents updated information as of September 30,1994. The data contained herein is 9 product of the NRC's Safety issues Management System (SIMS), which is mair'ttmed by the project management staff in the Office of Nuclear Reactor Regulation and by the staff in NRC's regions. The NRC has given significant attention to the quality review of TMI, USl, GSI, and other MPA implementation and verification data in SIMS. The agency has put-in-place severalinitiatives with the intention of reducing the number of administrative non-safety relevant requirements contained in licensing documents such as technical specifications. Because of the non-safety relevance of these items, the application for removal of these items from the license has been left to the option of the licensee. For purposes of completeness, these items were reported last year in Supplement 3 of NUREG-1435. However, because of the lack of safety relevance, these items are not being reported in this supplement. Supplement 3 provided updated information for 109 plants as of September 30, 1993. This report, Supplement 4, provides data for 107 plants. In order to directly focus attention on operating plants, this report excludes Browns Ferry 1 and Browns Ferry 3 which have been indefinitely shutdown since 1985. In 1993 the licensee declared the plants to have a Maximum Dependable Capacity (MDC) of zero, retroactive to June 1,1985. When these plants become active, the NRC will report the status of all remaining open safety issues. -vii-

Jhree Mile Island Action Plan Reauirements lmolementation Status. More than 99 percent of the TMI Action Plan items have been implemented at 107 licensed plants. Of the 12,678 applicable items,12,667 have been completed or closed and only 11 remain open from an implementation standpoint. Nine of the remaining 11 open items are projected to be implemented by the end of calendar year 1995. As noted in previous supplements, some slippages have occurred in projected implementation dates. All schedules for implementation of TMI Action Plan items remain within the timeframe previously reported to the Commission and to Congress. From an issue perspective, detailed control room design review items account for 7 of the 11 remaining open items. From a plant perspective, the TMI Action Plan requirements have been fully implemented or closed at 97 of the 107 licensed plants. Of the remaining 10 plants, each has 1 remaining item to implement, with the exception of Haddam Neck, which has 2 items. Verification Status. Tis have been issued for 78 individual TMl requirements to provide guidance for the field verification of licensee implementation. Of the 5,890 TMI items requiring verification, 5,859 (99 percent) have been completed. Unresolved Safety issues (USls) Imolementation Status. Approximately 94 percent of the USl items have been implemented at licensed plants. Of the 1,751 applicable items,1,646 have been completed and 105 remain open from an implementation standpoint. On average, each plant has approximately 1 remaining item to implement, and no plant has more than 3 items to implement. Three USis (A-44, Station Blackout; A-46, Seismic Qualification of Equipment in Operating Plants; and A-47, Safety implications of Control Systems) account for 97 percent of the unimplemented items. These three USls are in varying stages of NRC review and licensee implementation, as further described in Section 3.1 of this report. Verification Status. Six Tis have been issued to provide guidance for the field l verification of licensee implementation. These Tl designations correspond to USls A-7, Mark I Long-Term Program; A-9, Anticipated Transients Without Scram; A-24, i Qualification of Class 1E Safety-Related Equipment; A-26, Reactor Vessel Pressure Transient Protection; A-44, Station Blackout; and A-46 Seismic Qualification of Equipment in Operating Plants. -viii-

The requirements to perform field verifications have resulted in a total of 453 items to be verified at the 107 plants. As of September 30,1994, the NRC field verification had been completed on 313 (71 percent) of the required items. Generic Safety issues (GSis) Imolementation Status. Approximately 98 percent of the applicable items associated with GSis have been implemented at licensed plants. Of the 2,579 applicable items, 2,516 have been completed and 63 remain open from an implementation standpoint. On average, each plant has one item to implement, and no plant has more than 4 items to implement. Sixty eight plants have implemented all applicable items related to GSis. Five GSis account for 94 percent of the items for which implementation is incomplete. These GSis are specifically addressed in Section 4.1 of this report. Verification Status. Eight Tis have been issued to provide guidance for the field verification of licensee implementation. Of the 1,14, GSI items requiring verification, 1,055 (92 percent) have been completed. Q1her Multiolant Actions (MPAs) Imolementation Status. Approv.imatc'y 89 percent of the applicable items associated with MPAs have been implemented at licensed plants. Of the 6,951 Eu,licable items, 6,307 have been completed and 644 remain open from an implementation standpoint. On average, each plant has approximately 6 remaining items to implement, and no plant has more than 11 items to implement. No plant has implemented all applicable items related to other MPAs. Sixteen MPAs account for 97 percent of the items for which implementation is incomplete. These 16 MPAs are specifically addressed in Section 5.1 of this report. Verification Status. Seventeen Tis have been issued to provide guidance for the field verification of licensee implementation. Of the 882 MPA items requiring verification,633 (70 percent) have been completed. Conclusions After a detailed review of the implementation and verification status of TMl Action i Plan requirements, USIs, GSis, and other MPAs, the NRC staff has drawn the following conclusions-1 The NRC closure process for TMI Action Plan issues, USls, GSis, and other e MPAs is adequate for protecting the public health and safety. Licensees continue to make progress in implementing actions that are voluntary or that are imposed or requested by the staff. The framework exists to verify that open items are implemented in the future. -ix-

e The NRC continues to make progress in verifying the implementation actions that licensees reported complete. e The schedule slippages related to implementing TMl Action Plan items do not pose a threat to the public health and safety. The NRC staff will continue to maintain close oversight of the implementation actions and schedules proposed by the licensees to ensure that remaining TMI requirements are completed in accordance with regulatory requirements and within acceptable time frames. t P i .X-i

ABBREV'ATIONS ACRS Advisory Committee on Rete, tor Safeguards ATWS anticipated transient withNt scram BL bulletin B&O bulletins and orders B&W Babcock and Wilcox BWR boiling-water reactor BWROG Boiling Water Reactors Owners Group CE Combustion Engineering CPI containment performance improvement CRGR Committee for the Review of Generic requirements l DBA design-basis accident [ ECCS emergency core cooling system GIP generic implementation procedure GL generic letter GSER generic safety evaluation report GSI generic safety issue HPCI high-pressure coolant injection IGSCC intergranular stress corrosion cracking IN information notice (NRC) IPE individual plant examination IPEEE individual plant examination of external events IST inservice testing LCO limiting conditions for operation MOV motor-operated valve MPA multiplant action NRC U.S. Nuclear Regulatory Commission NRR Office of Nuclear Reactor Regulation (NRC) NUMARC Nuclear Management and Resource Council ODCM Offsite Dose Calculation Manual PCP process control program PORV power-operated relief valves PWR pressurized-water reactor PZR pressurizer RCIC reactor core isolation cooling RCS reactor coolant system RES Office of Nuclear Regulatory Research (NRC) RETS radioactive effluent technical specifications RG regulatory guide RHR residual heat removal RWCU reactor water cleanup SBL supplement bulletin SIMS safety issues management system -xi-

I SOER significant operating experience report SPDS safety parameter display system { SOUG Seismic Qualification Utility Group SRM staff requirements memorandum SSER supplementary safety evaluation report Tl temporary instruction TMl Three Mile Island TS technical specifications TU Texas Utilities (Elec.tric) USI unresolved safety Isse VlB vital instrument bus e b o 7 I k I h I L t -xii-

i 1 INTRODUCTION This fourth annual report, Supplement 4, updates the implementation and verification status of the Three Mile Island (TMI) Action Plan requirements, unresolved safety issues (USis), generic safety issues (GSis), and other multiplant l actions (MPAs). The NRC previcusly published three volumes of this NUREG series. Volume 1, published in March 1991, discussed the status of TMl Action Plan requirements. Volume 2, published in May 1991, identified the implementation and verification status of actions associated with USIs. Volume 3, published in June 1991, detailed the status of GSI actions. The first annual NUREG report, Supplement 1, combined these volumes into a single report and provided updated information as of September 30,1991. Supplement 1 was published in December 1991. The second annual NUREG report, Supplement 2, provided updated information as of September 30,1992. In addition, Supplement 2 also provided the status of licensee implementation and NRC verification of MPA issues not related to TMI Action Plan requirements, USIs, or GSis. Supplement 3 provided status as of September 30,1993. This fourth annual NUREG report, Supplement 4, provides updated information as of September 30,1994, for all TMI, USI, GSI, and MPA issues. Subsequent volumes will continue to be published annually to document the progress of implementation and verification of these items. The agency has put-in-place severalinitiatives with the intention of reducing the i number of administrative non-safety relevant requirements contained in licensing documents such as technical specifications. Because of the non-safety relevance of these items, the application for removal of these items from the license has been left to the option of the licensee For purposes of completeness, these items were reported last year in Supplement 3 of NUREG-1435. However, because of the lack of safety relevance, the items listed below are not being reported in this supplement. Sims Items MPA Title 1 GL-88-16 D021 Removal of Cycle-specific Parameter Limits GL-88-12 D022 Removal of Fire Protection Tech Specs GL-88-06 D023 Removal of Organization Charts i GL-87-09 D024 Mode Changes and LCO's - Tech Specs 3.0 and 4.0 GL-89-01 D025 Relocate RETS to Admin. Section of Tech Specs GL-89-14 D026 Elimination of 3.25 Requirement in Tech Spec 4.0.2 GL-90-02 D027 Alternative Reqmts for Fuel Assemblies in Tech Spec GL-90-09 D028 Visualinspection Frequency for Snubbers GL-91-01 D029 Removal of W/D Schedule for RV Material Specimens GL-91-08 D030 Removal of Component Lists from Tech Specs GL-91-04 D031 TS Surveillance Interval Requirements for 24 Mo. Cycle l GL-91-09 D032 Mod of Surv Int. for Elec Proto Assem in Power Supp GL-93-05 D033 Line item Tech Spec Improvement to Reduce Surv. Reg.. _ - - ~

GL-93-07 D034 Mod of Tech Spec Admin (Emergency and Security Leaks) GL-93-08 D035 Relocation of Tech Spec Tables RE: Instrument Resp. Time GL-94-01 D036 Removal of Accel Testing / Reporting Reg. for Emergency DG This report, Supplement 4, describes the implementation and verification status at the 107 licensed plants in the United States and makes this information available to interested parties, including the public. In order to directly focus attention on operating plants, this report excludes Browns Ferry 1 and Browns Ferry 3 which have been indefinitely shutdown since 1985. In 1993 the licensee declared the plants to have a Maximum Dependable Capacity (MDC) of zero, retroactive to June 1,1985. When these plants become active, the NRC will report the status of all remaining open safety issues. Supplement 3 provided updated information fm 109 plants as of September 30,1993. Included herein is information on the implementation and verification state.s of the TMI Action Plan requirements, USis, GSis, and other MPAs. For the 'G/ licensed plants, there are 12,678 applicable items for TMl Action Plan issJes,1,751 for USIs, 2,579 for GSis, and 6,951 for other MPAs. A total of 23 959 applicable items are addressed in this report. The information presented in this volume is current as of September 30,1994. 1.1 Backaround TMl Action Plan requirements, USIs, GSis, and other MPAs are all types of generic issues that originated from increased technical understanding of the safety of nuclear power plants. This increase in understanding occurred over time and resulted from operating events. research, testing, and experience. The specific origins of these issues and the development of requirements in each area, with the exception of other MPA's, were discussed in Volumes 1 through 3 of this NUREG series. The origin for other MPAs is discussed in section 1.3 of this supplement. Actions to be taken by licensees in response to these generic issues apply to more than one plant. The NRC evaluates the status of each licensee's implementation in conjunction with its evaluation of other NRC requirements, unique plant considerations, and interim measures. Similarly, the NRC authorizes a licensee to restart or begin operation of its plant only after carefully reviewing the plant's compliance with NRC requirements and evaluating the licensee's demonstrated capabilities to safely operate the plant. The NRC has allowed operation of a new plant, or continued operation of a licensed plant, when the licensee has not fully implemented all items discussed in this report only after ensuring that sufficient compensatory measures have been taken or after determining that plant operation presented no undue risk to the public health and safety. The data contained in this NUREG report are a product of the NRC's Safety issues Management System (SIMS), which is maintained by the Project Management _

i i l i Staff in the Office of Nuclear Reactor Regulation (NRR) and by NRC regional personnel. The NRC has given significant attention to the quality review of TMI, USl, GSI, and other MPA implementation and verification data in SIMS. P 1.2 Process and Accountability in 1989, the Commission adopted a six-step program for closure of generic safety issues. Although TMI requirements were treated separately, the process to achieve and verify closure of these issues is similar to that used for USis, GSis and MPAs. The overall NRC program consists of the following steps: Identifying Relevant Issues - Generic concerns are typically identified by the e NRC staff as a result of perceived problems at one or more operating nuclear power plants, or as a result of revised analyses pertaining to matters previously considered resolved. Issues may also be identified by others, for example, licensees, vendors, the Advisory Committee on Reactor Safeguards (ACRS), and the public. The NRC staff identified the TMI requirements by compiling and evaluating information from all available sources concerning the accident at l i TMI. i e Prioritizina Issues - Once identified, an issue is evaluated by the staff for its potential importance to nuclear safety. The staff classifies the issue and establishes a priority for resolution based on this evaluation and on other factors, such as value-impact analysis and risk assessment. The primary purpose of prioritizing issues is to assist in the timely and efficient allocation of resources to those safety issues that hava a high potential for reducing risk. Four priority categories are used: high, medium, low, and drop. A high priority ranking means that a concentrated effort is appropriate to achieve the earliest resolution practical. Resolvina Issues - The staff evaluates corrective actions that might be taken e to satisfactorily resolve a safety issue. In addition to using experience, tests, and experiments, the staff may use the results of analyses, probabilistic risk assessments, or other calculations in this evaluation. The staff uses the results of such work to propose the action or actions it would consider an acceptable basis for closing the issue. The evaluation may require NRC to change requirements or guidance. lmoosina Reauirements (USIs and TMI Action Plan Reouirements)- Each e affected licensee or applicant is required to prepare a schedule for implementing the resolution consistent with a rule, policy statement, regulatory guide, generic letter, bulletin, or licensing guidance developed during the resolution stage. The NRC staff evaluates the importance of the issue and determines whether it is to be imposed only on plants licensed after resolution of the issue, or if the required corrective actions should be backfit to existing plants. _

Reouestino Action (GSis)-The NRC staff evaluates the importance of an e issue and determines the types or classes of plants to which the resolution applies. The staff also determines whether corrective action is appropriate for existing plants or only for plants licensed after resolution of the issue. These corrective actions may be imposed on licensees in the form of a rule, policy statement, regulatory guide, generic letter, bulletin, or licensing guidance. Each affected licensee or applicant is required to prepare a schedule for implementing the resolution. Once an issue is resolved, each action to be implemented is assigned a multiplant action (MPA) number for tracking purposes. imolementino Actions - Licensees of affected plants take corrective actions to e satisfy commitments made in response to the imposed requirements (TMI Action Plan requirements and USIs) or the staff's request (GSis and other MPA issues). These actions may include modifications or additions to equipment, structures, procedures, technical specifications, operating instructions, and so forth. The role of the NRR Project Manager in implementing the resolution of a particular issue depends on the safety significance of the issue and the manner in which the issue is to be addressed. Significant TMI Action Pian requirements or USIs may require backfits to existing plants. Backfitting is imposed by rule or order unless the licensee volunteers to comply, in which case a confirmatory order may be issued. In any case, a deadline is set or negotiated for completing action at the particular nuclear plant. The Project Manager monitors licensee l progress toward closure and ensures that the work is completed by the j negotiated date. The Project Manager ensures that the Catus of the item is t properly documented for each plant. Verifvine'Imolerrentation - NRR staff members, NRC regional personnel and a NRC resident ir spectors ensure that licensees meet commitments made to the NRC for those issues requiring verification. Temporary instructions (Tis) have been issued to guide inspectors in verifying licenses implementation of l corrective actiorcs for certain generic issues that require plant hardware changes and subsequent verification by the NRC. Other issues may require engineering analysis to demonstrate continued safety of the plant, but require no specific plant configuration changes. For these issues, the NRC headquarters staff reviews and ensures the acceptability of each analysis, and no verification at ) the plant site is required. SIMS is designed to track issues from their identification through implementation of associated actions and field verification. The NRR Project Manager periodically obtains data pertaining to the licensee's implementation dates from meetings, site visits, and discussions with resident inspectors or the licensee. Recent NRC initiatives to improve the quality and the accountability of data include requirements that (1) any conclusion that a corrective action has been implemented i l be accompanied by a reference document from the licensee staff providing the basis for closure of the issue at the particular plant, and (2) the inspection report number and the date of the inspection be entered into SIMS if verification is required. 1.3 Definitions A number of terms are used to describe generic issues and their status. These terms are important not only because they categorize issues and their origin, but ) because their use implies both applicability and degree of completeness. For the purposes of this report, the following definitions apply: Generic Safety issue (GSil-A safety concern that affects the design, construction, or operation of all, several, or a class of nuclear power plants and may have the potential for safety improvements at such plan:ts. imolemented item - An item is implemented when a licensee has completed e the activities necessary to satisfy the requirements (or assumptions) made in the staff's technical resolution in accordance with commitments concerning the generic issue. 112m -The application of a TMI Action Plan requirement, USl, GSI or other e MPA issue to a specific plant. MPA - A multiplant action item originates from industry experience, new e regulations / requirements, or from resolution of generic issues resulting in the issuance of a generic communication requiring action by the licensees. TMl items, USIs and GSis are all MPAs; however, there are also other MPAs that do not fit into one of these categories. These other MPAs may be either required or voluntary. For the purposes of this report only, non-voluntary MPA issues are considered. TMI Action Plan item - An issue applicable to one or more licensed plants as e derived from NUREG-0737, Supplement 1, thereto, i Total Plant items - The theoretical maximum number of potential items e resulting from applying each issue (TMI, USI, GSI or other MPA) to all 107 plants. Total Aoolicable Plant items - The total number of applicable items determined e by reviewing the applicability of each issue at each of the 107 licensed plants. Unimolemented item -- An item is unimplemented when a plant has not e completed the activities necessary to satisfy the actions requested or required by the staff following the resolution of a particular generic issue. 5-A

Unresolved Safetv Issue (USl)- A matter affecting a number of nuclear power plants that poses important questions concerning the adequacy of existing safety requirements for which a final resolution has not yet been developed and that involves conditions not likely to be acceptable over the lifetime of the plants affected as identified in NUREG-0510 and subsequent annual reports to Congress.

Verification Comoleted - A licensee's actions to implement a technical e resolution for a generic issue have been inspected and verified by the NRC in accordance with the guidance provided by the applicable temporary instruction for that issue. /\\ l

2 THREE MILE ISLAND ACTION PLAN REQUIREMENTS This section describes the overall status of implementation and verification of TMI Action Plan items at the 107 currently licensed plants. This report excludes Browns Ferry 1 and Browns Ferry 3 which have been indefinitely shutdown since 1985. In 1993 the licensee declared the plants to have a Maximum Dependable Capacity (MDC) of zero, retroactive to June 1,1985. When these plants become active, the NRC will report the status of all remaining open safety issues. Supplement 3 provided updated information for 109 plants as of September 30, 1993. 2.1 Imolementation Status More than 99 percent of the TMI Action Plan items have been implemented or closed at licensed plants. Of the 12,678 items,12,667 have been completed and only 11 have not yet been implemented. Figure 2.1 presents the overall status of implementing the TMI Action Plan requirements. The 12,667 items completed at the 107 licensed plants have been disposed of as follows: A total of 12,285 have been implemented or closed by either incorporating fixes into the plant design before licensing or by implementing the necessary requirements at operating plants. A total of 382 items have been superseded and the associated requirements 1 have been effectively addressed by other items or through other regulatory means. The superseded items are discussed in detailin Volume 1 of NUREG-1435. The following observations are made about the remaining 11 unimplemented items: Nine of these items are projected to be implemented by the end of calendar year 1995, as shown in Figure 2.2. Licensees continue to make progress toward implementation of the remaining items. As noted in previous status reports, some slippages have occurred in projected e implementation dates. Refueling outages account for a number of slippages in the implementation of remaining TMl items. All schedules for implementing the remaining TMI Action Plan items are within the timeframe previously reported to the Commission and to Congress. From an issue perspective, detai ed control room design review items account for 7 of the 11 unimplemented items, as shown in Table 2.1. 7 .O-

l f TMI ACTION PLAN REQUIREME. TS N IMPLEMENTATION STATUS AT LICENSED PLANTS l 3co =. OVEMVIEW 254 i 2so -- ,,3 scono. 1s,4o4 207 aos es 200 -- N O 15000-12,578 1 156 yg a g tso - 5 123 6

tocoO 5g 11e t

g too.. as 61 i 5000 so -. O o I i i 1 I I I I I I I i I i 1 0 g a a e i a g i e N June 1989 af3eet 12/31JBe 30090 7f3190 Sf304012f31/go 2fMt91 8/3091 Sf3091 1/31/92 2/3192 Sf3192 af3tW92 Sf3W93 trJO94 DATE OF STATUS REMRT mese notese do not enesude lemme for Brooms Ferry 1, Broome Ferry 3, FL St. Vrain, Rancho Se:n, Sen Onc4e 1, Shoreham, Troien and Yanhoe nome paents. These plants are permaneney or indennneer shut daem. The noemi number et scensed piente coneadored in this report is 107. Figure 2.1

PROJECTED SCHEDULES FOR REMAINING TMI ITEMS ITEMS NOT IMPLEMENTED AT END OF CALENDAR YEAR 100 JUNE 1989 SCHEDULES 75 -- l l CURRENT SCHEDULES 61 5 46 50 -- 31 19 25 -- 15 14 12 o i i .g i i..__. 09/93 12/93 12/94 12/95 12/96 12/97 09/93 12/93 12/94 12/95 12/96 12/97 JUNE 1989 SCHEDULES

31 19 15 14 12 0

09/30f94 SCHEDULES

61 46 6

3 2 0

Based on dates of items listed as not implemented Figure 2.2

i

SUMMARY

OF THE REMAINING TMI ITEMS BY AREA AREA OPEN o Relief & Safety Valve Test Report 1 o Instrumentation for Detection of inadequate Core Cooling 2 l 1 l 9 o Control Room Habitability 1 o Deidiled Control Room Design Review 7 l TOTAL 11 i l Table 2.1 l l

- e From a plant perspective, the TMl Action Plan has been fully implemented or ~ closed at 97 of the 107 licensed plants. Table 2.2 summarizes the 11 unimplemented items by plant. Ten plants account for the remaining 11 items. Haddam Neck has 2 items and the remaining plants have 1 item each to implement. Appendix A lists the unimplemented TMI items by issue and gives projected implementation dates. t 2.2 Verification Status ~ For generic items, such as the TMI requirements, the Office of Nuclear Reactor Regulation issues temporary instructions (Tis), when appropriate, to specify which ) requirements are to be verified by the NRC after licensees have implemented the corrective actionr, specified in the resolution. The NRC performs these inspections, consistent with other inspection priorities, to verify proper implementation of the requirements. Verification is not considered complete until the NRC conducts the required inspection in accordance with the TI, and issues an inspection report documenting that the licensee has adequately satisfied the requirements. On occasion, there may be issues for which the verification requirements according to the Tl are completed before the licensee has fully implemented all aspects of the issue. Tis have been issued for 78 individual TMl requirements, which ccver a total of 6,373 items at the 107 licensed plants. Upon initial inspection of certain items and further review by the regional offices,483 items covered by the Tis were found to be inapplicable frcm a verification standpoint, leavireg a net total of 5,890 items _ requiring verification. The majority of items found not applicable are cases in which initial inspections did not reveal any significant findings and for which further inspection effort cannot be justified. As of September 30,1994, 5,859 items (99 percent) had been verified. Only 31 items remain to be verified, including some items not yet implemented by licensees. I A

l l.

SUMMARY

OF THE REMAINING TMI ITEMS BY PLANT PLANT OPEN Diablo Canyon 2 1 Dresden 3 1 Ft Calhoun 1 Haddam Neck 2 Millstone 1 1 Nine Mile Pt 1 1 Pilgrim 1 1 Quad Cities 2 1 Surry 1 1 Surry 2 1 l Table 2.2

f A

I 2.3 Status by Plant Table 2.3 presents summary information on the status of TMI Action Plan items (except superseded items) at all licensed plants. For implementation, the table shows the number of applicable items, the number of items completed, the percentage completed, and the number of items remaining. For verification, the table shows the number of items covered by Tis at each plant, the number requiring verification, the number completed, and the percentage completed. Appendix A lists the unimplemented items by issue and giees projected implementation dates. From an implementation standpoint, the TMI Action Plan has been fully implemented at 97 of the 107 licensed plants. From a verification standpoint, all required inspections have been completed at 80 of the 107 licensed plants. Twenty three plants have one item each to be verified and the remaining 4 plants have 2 items each. i l 5AFETY ISSUE MANAGEMENT SYSTEM STATUS OF TMI ACTION PLAN -

SUMMARY

BY UNIT IMPLEMENTATION VERIFICATION ITEMS ITE MS PER CENT ITE MS ITE MS ITEMS IYEMS PER CENT DMIT APPLICABLE COMPLETED COMPLETED REMAINING COVE RED REQUIRED COMPLETED COMPLETED ARKANSAS 1 122 122 (100) O S2 $1 Ft i100) ARKANSAS 2 112 !!2 (100) 0 59 58 58 1 let) BE AVE R VALLEY 1 117 117 (100) e 62 81 61 i 100) BEAVER VALLEY 2 126 128 (100) O S2 57 57 l 100 I BIG ROCK POINT 1 104 104 (100) e SS 50 54 l 100 l BRAIDWOOD 1 126 128 (100) O S2 58 56 l 100 i tRAIDWOOD 2 126 126 (100) O S2 56 SS i 194 i SROWNS FERRY 2 110 110 (100) 0 57 51 50 98 SRUN9 WICK 1 110 110 11001 0 57 51 51 tot BRUNSWICK 2 110 110 (100) 0 57 51 51 100 LYRON 1 128 126 (100) e 62 58 58 l 199 I CYRON 2 128 126 (100) e 82 58 58 l 10e t CALLAWAY 1 123 123 1100) e Se et Se tot I CALVERT CLIFFS 1 113 113 (100) e 59 53 53 i 100 l '. CALVERT CLIFFS 2 113 113 (100) e 59 53 53 1 100 36 CATAWBA 1 128 126 (100) e S2 80 59 ! 98 i e CATAWSA 2 128 126 (100) O S2 S2 S1 1 98 CLINTON 1 126 120 (100) 0 55 56 56 i 100 l COMANCHE PEAK 1 119 119 (100) 0 55 50 50 i 100 COMANCHE PEAR 2 120 120 (100) 0 SS 53 53 l 199 COOK 1 117 117 (100) e 82 55 55 l 100 i COOK 2 117 117 (100) O S2 55 55 I lee COOPER STATION 110 110 (1901 0 57 51 51 1 100 i CRYSTAL RIVER 3 122 122 (100) O S2 SG 54 i 96 i DAVIS-5 ESSE 1 121 121 (100) e 51 55 55 i 100 i DIA8LO CANYON 1 128 126 (100) O S1 55 55 1 194 i DIA8LO CANYON 2 128 125 (99 ) 1 61 57 57 l 10e DRESDEN 2 110 110 (100) e 58 52 51 l 98 i DRE5 DEN 3 119 109 (99 ) 1 58 52 51 98 DUANE ARNOLD 110 110 (100) e 57 54 54 100 i FARLEY ! 118 118 (100) O S2 56 SS 100 I FARLEY 2 128 128 (100) O S2 SS SG 1 100) FERMI 2 120 120 (100) 0 56 54 50 (109 1 FITZPATRICK lie 110 (IOO) 0 57 56 Se i 194 i FORT CALHOUN 1 113 112 (99 ) 1 59 55 54 1 SS i GINNA 118 116 (100) O Gl SS 56 100 1 GRAND GULF 1 120 120 (1003 0 58 50 59 l 100 MADDAM NECM 117 115 (98 3 2 82 55 54 1 98 i 100 t MARRIS 1 125 125 (100) O S1 89 Se i MATCH I ile 110 (100) 0 57 57 57 . 199 MATCH 2 110 110 (100) 0 57 57 56 1 98 100 HOPE CREEK 1 120 120 (100) 0 SS 50 50 i i INDIAN POINT 2 118 118 (100) O S2 59 59 (ISS I INDIAN POINT 3 117 117 (1003 0 $2 59 59 (100l Table 2.3

5AFETY I S S (J E MANAGEMENT SYSTEM STATUS OF TMI ACTION PLAN - SUp94ARY SY UNIT IMPLEMENTATION VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEnts PER CENT UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQUIRED COMPLETED COMPLETEC KEWAUNEE 117 117 (1001 0 62 58 ST (96 (100) LASALLE 1 120 120 (100) 0 56 52 52 1 LASALLE 2 120 120 (100) 0 56 52 52 (200J LIh4ERICK 1 120 120 (1001 0 56 52 52 (100 i LIHERICE 2 120 120 (100) 0 56 50 50 (100 i MAINE YANMEE 113 113 (100) 0 59 56 56 (1001 MCGUIRE 1 127 127 (100) 0 62 62 61 198 ) MCGUIRE 2 127 127 (100) 0 62 62 61 98 l MILLSTONE 1 109 108 (99 1 1 56 46 45 i 97 i MILLSTONE 2 113 113 (100) 0 59 54 54 1 100 i MILLSTONE 3 127 127 (100) 0 62 58 58 ! 100 MONTICELLO 110 110 (1001 0 57 51 51 1100) NINE MILE POINT 1 107 106 (99 1 1 56 54 54 (100) NINE MILE POIhT 2 119 119 (100) 0 55 52 52 (100) ,C00TH ANNA 1 118 118 (100) 0 62 60 60 (100t aN02TH ANNA 2 128 128 (100) 0 62 60 60 (100 I m0COMEE 1 122 122 (100) 0 62 57 56 (98 i

DCONEE 2 122 122

- 100) 0 62 58 57 (98 OCONEE 3 122 122 l 1001 0 62 58 57 (38 1 OYSTER CREEK 1 107 107 1100) 0 5* 47 47 (100 I PALISADES 113 113 (100) 0 5. 51 51 1 100 l } POLO VERDE 1 120 120 (100) 0 59 52 52 1 100 i PALO VERDE 2 120 120 (1001 0 59 53 53 i 100) PALO VERDE 3 120 120 (100) 0 59 54 54 i 100) PEACH BOTTOM 2 110 110 (100) 0 57 51 51 1 100i PEACH BOTTOM 3 110 110 (1001 0 57 51 51 i 100 i PERRY 1 120 120 (1001 0 56 55 55 100 l PILGRIM 1 110 109 99 1 1 57 48 48 100 1 POINT BEACH 1 117 117 100 0 62 56 56

100 POINT BEACH 2 117 117 100')

0 62 56 56 i 100 PRAIRIE ISLAND 1 117 117 (100) 0 62 52 52 1 100) PGAIRIE ISLAND 2 117 117 (1001 0 62 53 53 1100) OUAD CITIES 1 110 110 (100) 0 57 51 50 (98 ) OUAD CITIES 2 110 109 (99 1 1 57 51 50 (98 i GIVER BEND 1 119 119 (100) O 56 50 50 E100 i ROBINSON 2 117 117 (100) 0 62 56 54

96 i

SALEM i 116 116 (100) 0 61 54 5' . 96 SALEM 2 127 127 (100) 0 62 57 55 l 96 SAD ONOFRE 2 122 122 (100) 0 59 53 53 l 100 SAO ONOFRE 3 122 122 (1001 0 59 55 55 1 100 i SECBROOM 1 127 127 (100) 0 62 57 57 (100 l SEQUOYAH 1 127 127 (100) 0 62 56 56 (100 1 SEQUOYAH 2 127 127 (1001 0 62 58 58 (100! SOUTH TEXAS 1 126 126 (100) 0 62 56 56 (100! Table 2.3

s J k SAFETY ISSUE MANAGEMENT SYSTEM STAYUS OF TMI ACTION PLAN - SUte4ARY BY UNIT IMPLEMENTATION VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PER CENT UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQUIRED COMPLETED COMPLETED SOUTH TEXAS 2 126 126 (100) 0 62 56 56 (100) ST LUCIE 1 113 113 (1001 0 59 55 55 (100l ST LUCIE 2 122 122 (1001 0 59 54 54 (100 l SUP99E R 1 127 127 (1001 0 62 61 61 (100 t SURRY 1 117 Ilo (99 1 1 62 56 56 (100 l SURRY 7 117 116 (99 ) 1 62 56 56 (100 l SUSQUEHANNA 1 120 120 (100) 0 56 56 56 (100 1 SUSQUEHANNA 2 120 120 (100) 0 56 56-56 (100 i THREE MILE ISLAND 1 128 128 (t001 0 62 55 55 (100 i TURMEY POINT 3 117 117 (100) 0 62 60 59 (98 TURMEY POINT 4 117 117 (100) 0 62 60 59 (98 I i I VERMONT YANMEE 1 110 110 (1001 0 57 53 53 (100 I e V0GTLE 1 124 12C (100) 0 60 54 53 (98 i ^ V0GTLE 2 124 124 (100) 0 60 56 55 (98 O WASHINGTON NUCLEAR 2 170 120 (1001 0 56 55 55 (100 1 WATERFORD 3 121 121 (100) 0 59 55 55 1 101 WOLF CREEK 1 126 126 (100) 0 60 54 54 1 100 t ZION 1 117 117 (100) 0 62 60 59 l 98 ) ZION 2 117 117 (100l 0 62 60 59 i 98 ) TOTALS / AVERAGES 12678 12667 100 11 6373 5890 5859 99 Table 2.3 -. ~..

i 2.4 Status by issue l Table 2.4 summarizes information on each TMI issue. For implementation, the table shows the number of applicable plants, the number of plants comple+ed, the percentage completed, and the number of plants remaining. For verification, tu, table shows whether the issue requires verification, the number of plants covered by the TI, the number of plants requiring verification, the number of plants completed, and the percentage completed. Of the 172 TMl Action Plan issues,164 have been fully implemented and 4 have been superseded. Four categories of TMl Action Plan issues account for the 11 TMI requirements to be implemented. Detailed control room design review accounts for 7 plants yet to complete implementation, i

SAFETY ISSUE MANAGEMEN T SYSTEM STATUS OF TMI ACTION PLAN - SUPO4ARY BY ITEM IMPLEME4TATION VERIFICATION PLANTS PLANTS PE R CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLE T E D REMAINING REQUIRED COVERED REQUIM D COMPLETED COMPLETED 67 4 1 72 72 (1001 0 NO REACTOR COOLANT PUMP TRIP GL-83-02 107 107 (2001 0 NO MUREG-0737 TECHNICAL SPECIFICATIONS GL-83 36 107 107 (2001 0 NO MUREG-0737 TECHNICAL SPECIFICATIONS IA 1.1.1 107 107 11001 0 YES '07 107 107 (1001 SHIFT TECHNICAL ADVISOR - ON DUTY IA 1.1 2 10V 107 (1001 0 NO y' SHIFT TECHNICAL ADVISOR - TECH SPECS I A.I.1 3 107 107 (1001 0 YES 107 107 107 (100) SHIFT TECHNICAL ADVISOR - TRAINED PER LL CAT 8 I A 1.1 4 107 107 (1001 0 NO SHIFT TECHNICAL ADVISOR - DESCRIBE LONG TERM PROGRAM I A.I.2 107 107 (100) 0 YES 107 107 107 (100) SHIFT SUPERVISOR RESPONSIBILITIES 1.A 1.3 1 107 107 (1001 0 YES 107 107 107 (1901 SHIFT MANNING - LIMIT OVERTIME I.A 1.3.2 107 107 (2003 0 YES 107 107 107 (100) SHIFT MANNING - MIN SNIFT CREW I.A.2.1.1 108 tot (1bJ) 0 NO 1908EDIATE UPGRADING OF RO & SRO TRAINING AW OUAL. - SRO EXPER. I A 2.I 2 ISS 106 (1001 0 NO IPO4EDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - SRO'S BE RO*S 1YR I.A 2.1.3 106 IOS (1001 0 NO IPO4EDIATE UPGRADING OF RO & SRO TRAINING A W QUAL. - 3 MO. TRAINING I.A.2.1.4 10s 106 (100) 0 YES 100 106 106 (100) Ipe4EDIATE UPORADING OF RO & $80 YRAINING A 2 QUAL.. MODIFY TRAINING I.A 2 1 S 106 106 (1001 0 NO IpesEDIATE UPGRAOING OF RO & SRO TRAINING A E QUAL. - FACILITY CERTIF. Table 2.4

TD.. NE .ET. 1 ) 1 1 3 ) 1 ) I .CE 9 0 9 9 9 9 9 9 9 L. 9 9 9 9 9 9 9 9 9 P. 1 1 1 1 1 1 1 1 .RM. ( ( ( ( ( ( ( ( l EO. .PC D. E .ST. .TE. .NL. 7 7 7 7 7 7 7 AP. 0 9 9 9 4 0 0 9 9 LM. 1 9 1 9 1 1 1 1 1 .PO. C N. O D. I.SE. T.TR. A I.NI. C. 7 7 7 7 7 7 7 F.AU. 9 9 0 9 9 9 9 0 9 LQ 1 9 1 9 1 1 1 1 1 IPE.. R. R E. V.. D. M .SE. TR.. 7 7 7 7 7 7 7 7 7 NE 0 9 0 0 9 9 9 0 9 E .AV. 1 1 1 1 1 1 1 1 1 .LO T .PC Y M D E T E. S S S S S S S S S R.O I I 0 O O O E E E E E E E E E Q.N U. N N N Y Y V Y Y Y Y Y Y Y Y B R E N Y R E A 4 M M t G. E S SN. 4 S E D E C G .TI NN.0 0 0 0R 9 9 9D eE 0D eO 0 0 0 0 AI E O I C I R 2 A N A . LA D T U O U P PM. N L A A G R G E R L P E e P A R. G U L S H N M L E A I t M O G I S A S N V a I N S T N I A E T E I N A V E R T C P S M A E E R TD.. O S T L R R A .NE.1 C A I P S E )S 1P 1W t 1 1. 1. 1S 1R ) ) 1 1 I .ET U M 3 0 0 t 9 0L 9l 0T 9D O 9 0 0 .CE.0 0E 0E 0S e 9 9O 9o 0D 9C S 0 0 0 L.0 T N. P 1S 1S 2T l 1 1O 1o 1C 1C I 1 1 1 S ORM1 ( (A (A (N s ( (C (C (C (A ( 1 ( I F S O I.EO E E A O A T.PC. R R L E E A. C C P A R R I S N N C O O S U T. N I I R R O C C S T T A E. O O L T N M T T N E T D. A A 8 Q Q E I Y S E.SE. S S L L S E E I S L. P.TT.7 M M U D D S N T NE 7A 7A 0M e 7-7A 7A 7N 7A 7 7 7 7 M.AL.0 0X 0X 7I S 0 9N 9M 0A 9R 0 0 0 9 E I.LP.1 1E 1E S S T 1W 11 1I 1R 1T 1 1 1 1 N E T .PM F O G G E I A C. N N M V S I I S S E E S M S S M M G R V. Y V V S A N N A A A E E E E E R E E X X N S R R R R E t* G C C E E 4 E U Y C 4 E. O I I 9 R S S S S D T N U E E E E E I E L. R L L S8 P C C D R R R R C L I 7R TR 0I 9 7E 7U 7U 7U 7U 7O 7I 7 7R . TA 7 0O SO 7L 5N 9C 0D 0D 9D 9D 9R 0B 9 9E NC.0G AI N 1F IF O 1O 1E 1E 1E 1E 1P 1I 1 1P .LL.1 I R R I R C C C C S X N A A O O T P O O O O R N E .PP I I I F F A R R R R E O P. Z P P P P V P G A A R R I O S M R E E T T T T T N T N E S I I I I I A N O C C C C R D O D. O. D. R R S T U E A F R R R R G E T R C R O I I I I I O C E . N C C C C C F S A P . O F C C C C C E I O I E E E E O A A A A A I V M T P P AP P L R O F . A O O O O N M M M M M E E O O M. R 1C

7. S sC O

R AR

8. E AR 8R R

P R C R t. .S S I E E E E U K T .S Y.

2. T

2. T.

3. T.

3. T S

L C I.3S 1 1 1 2T 1T O A I E E E E A

2. F

3. F S. D T

T 4R S

2. I

3. I 1U 1T IT 1T IT IT N 3S 3S S

T I .I i .L .R .R .R .R .RO CI CI C. O CE V AV AV A CO CO C. O CO C. H N E AM AE B. V H H H H M H D E E E .IA IR IR IR R IE IS IS IS IS IS I? 1S IC IF

TD.. NE.) ) 1 1 1 ET 0 0 0 0 . CE.0 L 0 0 0 0 0 P.1 1 1 1 1 RM.( ( ( ( 1 EO . PC D. E . ST . TE 6 0 NL.7 9 9 0 0 AP.0 4 3 1 1 LM.1 PO. C N. O I D. A.SE. T. C TR.7 NI S 0 0 9 9 O 0 I.AU.1 LQ 4 3 I 1 F.PE. I . R R. D.. M t k 7 7 7 7 .E 7 0 0 0 0 AV.0 E 1 1 1 1 LO.1 T PC. S Y M E D. S T E.S S S S S I R.E O O O 0 E E O O O O E E O O I U.Y N N N N Y Y N N N N Y Y N N Y G T B E. N Y R4 R E A 4 M M t E S G. SN. G . TI . NN.O O 0 0 0 0 0 0 0 0 0 0 0 0 0 4 A N . AI LM. 2 A P N L I P E. A R. e N l M O b I T a C E . NE. E T A . TD. D I . ET .) 1 1S 1 1 1 1T 1 1S 1 1 1 1 1 1 .0 0 0C 0 0 0 0N 0 0C 0 0 0 0 0 0 U M . CE.0 0 0O 0 0 0 0E 0 0O 0S 0 0) 0 0 0 T L. 2 1R 1 1 1 1M 1 1R 1T 1 18 2 1 1S N. P.1 S 1 (E ( (P (L ( ( ( ( (S (N t O.R* 1 ( (P ( F O L U T E 5 O T Eo. I PC. S I D P S A C E M R T E M S E C C I S A. I A E P L I T R A U T. T R M I L S L L N. T I G E S R A Y E A L E A E. V O L C T L T N ( R M T Y S E. D. I R O S S L A G S U L T P T E N U E N S T S P SE. TT. C N N D I F S T I T N S T . NE 9T 9O 7 7 7 9O 9I 9N 7N 7E 7S 7 7A M.AL 7A 7 0 0-0- 4P 4M 4I 0E 0V 0E 0 0 I 0 4S 4I 4R E . LP 1G E S O 1 1 1 O 9 A 1V 1 1R 1 1o N T N F E E E R U R L U T PM. F O I E L L L P S T N L D A C. T R C C O O O G A E S A E S O S S S I T C N S R W A R N N N S S O O E O P O O O G G G E N R I P P R C C C N N N D I P S T O E Y I I I N C E. W W C Y Y Y T T T O A L. F O O N A A A S S S I . SB O L P E L L L E E E S S S S E 9 9 7G 7P 7P 7P 9T 9T 9T 7T 7T 7T 7E 7V TANC7 0E 4. 4 4R 0S 0S 0S 4 4 4 0N 0N 0N 0D 0I 1C E 1I 1I 1I R R R 1E 1E 1E 1 1T AI. N C C M D D D E E E V V V W C LL. PP. O O E W W W E E P R R R R R O O O M M M I R 9 A. R P P D E E E P P P E E E V R O E T T T T T T E O F F F T E E E N W W S S S R C R O C C M A O O Y Y Y p I V. v. E A 'A A L L L S S S EP L R R R E A A A G G G T T T G G T E [ S P P P N N N N N N N N C R R I I I A A A I I E F Y Y Y R R R L L L D D R R R O T T T U U U O O O L L M. R O 0 E E E D D D O O O E E E O D ) N F F F C C C I I T C N M O A A A G G G 1-2- 3-1H H

2. S

!E 2E M 1S 2S

3. S 1N 2N 3N

.R R .R .S I. Y .V .V .I .I .I 1O 1O 1O 2T 2 7 7 8T 2T 2T 2T 1N 1N 1N .T T .T T . 6D S S O N N N .I .I I C BC C N BN .CR CS C.S CL D. L D. L D. L GA GA GA B. A B. A B. A S A A A A A E S I R R R IE IE !E IL IL .IV IN 1N IP IP IP IP IT IT IT IR IR !R IP IP ,\\O* ) f I

SAFE 7Y I5 SUE HANAGEHENT STSIEM STATUS OF TM! ACTION PLAN. sun *4ARY BY ITEM INPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED 11 n 2.3 107 107 11001 0 YES 107 107 107 (1001 PLANT SHIELDING

PLANT MODIFICATIONS (LL CAT 8)

IIB 31 108 106 (1001 0 YES 108 fee 106 (1001 POSTACCIDENT SAMPLING - INTERIM SYSTEM II B 3.2 107 107 !!001 0 NO POSTACCIDENT SAMPLING - CORRECTIVE ACTIONS II 8 3.3 106 106 (1001 0 WO POST ACCIDENT SAMPLING - PROCEDURES II B 3.4 107 107 1001 0 YES 18 F 197 109 199 I POSTACCIDENT SAMPLING PLANT MODIFICATIONS (LL CAT (el ,mY II B 4.1 107 107 (100) 0 NO TRAINING FOR MITIGATING CORE DAMAGE - DEVELOP TRAINING PROGRAM II B.4 2.A 107 107 (1001 0 YES 107 107 107 (1901 TRAINING FOR MITIGATING CORE DAMAGE - INITIAL 11.8 4 2.8 107 107 (2001 0 YES 107 10* 197 (100) TRAINING FOR MITIGATING CORE DAMAGE COMPLETE II.D 1.1 107 107 (1001 0 NO RELIEF & SAFETY VAlvt TEST REQUIREM NTS - SU9MIT PROGRAM II.D 1.2.A 107 107 (1001 0 WO RELIEF & SAFETY VALVE TEST REQUIREM NTS - COMPLETE TESTING II.D 1.2.8 197 107 (180) 0 NO RELIEF & SAFETY VALVE TEST REQUIREMNTS - PLANT SPECIFIC REPORT II.C 1.3 89 68 (98 ) 1 NO RELIEF &,AFETY VALVE TEST REQUIREM NTS - ELOCM-VALVE TESTING e YES 107 107 197 (190) (199)_ VALVE POS II.D 3 1 107 107 VALVE P05ITION INDICATION. INSTALL DIRECT INDICATIDMS OF 11.0 3 O 197 197 ItotI e NO WALVE POSITION IlmICATION - TECW SPECS II.E 1.1.1 72 72 (1003 e NO AFS EVALUATION.An4 LYSIS TatWe 2.4

SAFETY IS$UE MANAGEMENT SYSTEM STATUS OF TMI ACTION PLAN - SUP99ARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PE R CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED If E 1 1.2 71 71 (1003 0 YES 71 71 71 (100) AFS EVALUATION. SHORT TERM M005. II.E.1.1.3 72 72 (1001 0 YE S 72 72 72 (100) AFS -LONG TERM MODS. II.E 1.2.1.A et 56 11001 0 YES OS et 84 (1993 AFS INITIATION & FLOW-CONTROL ORADE II.E 1.2.1.8 72 72 (1001 0 YES 72 72 72 (1001 AFS INITIATION & FLOW - SAFETY ORADE y II.E 1.2.2 A SF 67 (1001 0 YES 57 87 67 (100) AFS INITIATION & FLOW - FLOW IteUCTION CONTROL GRADE g II E 1.2.2.8 72 72 (1001 0 NO AFS INITITATIOk & FLOW - LL CAT A TECH SPECS. II E 1.2.2 C 72 72 (2001 0 YES 72 72 72 (1993 AFS INITITATION & FLOW - SAFETY ORADE II E. 3.1.1 72 72 (1001 0 YES 72 72 72 (100] EMERGENCY POWER FOR PRESSURIZER MEATERS - UPGRADE POWER SUPPLY II.E.3.1.2 72 72 (1001 0 NO EIERGENCY POWER FOR PRESSURIZER HEATERS - TECH SPECS II.E 4.1.1 105 105 11001 0 WO DEDICATED HYDROOEM PENETRATIONS - DESIGN II.E 4.1 2 105 105 (1001 0 YES 105 tot 100 (1901 DEDICATED HYDROGEN PENETRATIONS - REVIEW & REVISE H2 CONTROL PROC II.E 4.1.3 195 105 (1001 0 YES 105 162 102 (1001 DEDICATED HYDROGEN PENETRATION - INSTALL II.E.4.2 1-4 107 107 (1001 0 YES 107 107 107 (1001 CONTAIMENT ISOLATION DEPENDABILITY - IMP. DIVERSE ISOLATION II.E 4.2.5.A IST 107 (1001 0 NO CONTAINMENT ISOLAT. DEPENDA8ILITY - CNTMT PRESS. SE T P T.. SPECIFY PRESS. II.E.4.2.5.8 197 107 (2001 0 YES 107 106 105 EDS 1 CONTAINMENT ISOLATION DEPEleABILITY. CNTMT PRESSURE SE TPT. MODS. TaIHe 2.4 i

~ TD NE .CE 3 ET ) ) ) ) ) 1 ) I 1 1 L.9 0 0 0 0 0 0 0 9 9 0 0 0 0 0 0 5 1 0 . P.1 9 1 1 1 1 1 1 9 9 1 RM.( 1 ( ( ( ( ( ( 1 1 ( EO ..PC. D.. E ST. .TE NL 0 3 7 7 7 7 7 6 AP.0 0 0 0 0 0 0 0 9 4 2 LM 1 1 1 1 1 1 1 0 9 7 PO 1 C. N O I D. T.SE. A.TR. C.AU 0 NI 4 7 7 7 7 7 0 3 0 0 0 0 0 0 0 0 2 0 2 I.LQ.1 F 1 1 1 1 1 1 1 7 1 7 R PE. I. R. E. V. D. M SETR.7 7 7 7 7 7 7 7 0 NE 0 0 0 0 0 0 0 0 2 0 2 E AV.1 1 1 1 1 1 1 1 7 1 7 T . LO. PC. Y M D E E S T I R.S S S S S S S S S S S E O O E E E E E E E O E E O E I Y N N Y Y Y Y Y Y Y N Y Y N U.Y Y Q T B E N Y tl R E A 4O M PU G. E S SN. .TI 4 S R G . NN.0 0E 0 0 0 0 O 0 0 0 0E 0 2 0E 0P A N AI V T R M D S 2 LA. L E E T A A PM. A M H A R H N L V T T G C e P E. R L O N P E A l N E O M U T b M O G O R a I R C C T T U B S S C P U E N D D T TD. S D I N M A N I I NE.1S E 1 1 1 1 1 1 1 1 1-1- 1L 1 1 1O I .ET U M .CE.0V 0E 0 0 0 0 0 0 0 0 0 0 0 0L 0E T L 0L 0 0 0 0 0 0 0 0 0G 0G 8D 0E 0L P.1L 1A 1 1 2 1 1 1 1 2 8N lN 9D 2V 1V S N O.RM 1N ( ( ( ( (R ( ( ( 'I (I 1A (E (E I.EO (A F V G O L L L L S O I T O O L T.PC. E S G I O O L I S A. G S N N C C T U T. N R N C I O S S S T A E. U O E L M E E N E E T M. P I P P L R R I V V Y S E. D. T S M E E O O L L L.SE. T A A G V C C G A A P. M I H S N E E N N V V M.TT T NE 7D 7C 7 7 7 7A 7R 7L 7E 2E 7E 4L 2 2 .AL.FT 0N 0A 0E 0 0 0E 0R 0U 0 0G 7T 0T 0C 7K 7K E I LP 1C 1R 1T 1 1R 1T 1 - 1S 1R 1O A 1A 1 C C O A H S E R U U E O O .PM. F O T L G E T D Q Q R L L A C. I U I R A Y E E O B. B. Y Y Y N C H P W M D D C S T T T O I A A F F I I I M T T T T T N N Q E E L L L S R N N N N I I E I I I I I E S A E E E E D L L M M M F F A E E E. B B B R A P P N N N O O N R R L. A A A U G / M SB. D D D D E I I I I I TA. 7N 7N 7E 7E 7N 7A 7A 7A 7A 2. 7. 0 2R 2R AI 7N . NC 0E 0E 0E 0C 0L 0I 0T 0T 0T 0T 7T 0T 0F 7E 7E 1P 1P 1O 1B 1D 1N 1N 1N 1N C 1C 1O Z Z LL 1P E E E R O G O O O O E E I I .PP. D D D P N I C C C C T T R R P E E T U U A. N N N D D C S S O O O E S S I I I G G G G G G G R R T E E T T T N N N N N N N O O E R R A A A I I I I I I I F F D P P L L L R R R R R R R + . O O O O O O O O O O N N R R R S S S T T T T T T T O O O O O I I I I I I I I I I I I F F F N N N N N N N T T T T T O O O O O O O A A M P M. 7N 8N M A. M

8. N CM D. M EM F. M T

T T P E.6N E E E N N A P P U I 2M 2M

2. N

2. T 2T

2. T 2T 2T 2E 3E 4T 1U

2. S T.

M 1T T M N .N N N N .N N .M M N S aI 4I 4I lE 1E 1E IE 1E lE 1E 2U 2U 2M 1 1 A .A .A .D D D .D D D D R R R R R I E GE N N N C C C F. C F. I FI F. I F. T FT F. T G. W ET ET E. T FI F. I FI C C C S S S W IO IO IO IC IC IC IC IC IC IC IN IN IN TO IO .IC IC IC IA IA IA IA IA IA IA II II II IP IP e0d* 7C

TD.. NE. ET l ) ) ) ) . CE. 0 0 0 0 L. 0 0 0 0 4 P 1 1 1 1 8 . RM ( ( ( 1 ( . EO. . PC. D. E. . ST . TE. NL 7 7 0 . AP. 9 0 0 0 1 . LM 5 1 1 1 5 PO. C N O I D.. T.SE. A.TR. C NI 7 7 6 I AU. 9 0 0 0 0 F 5 1 1 1 9 I LQ. R.PE R E. V D. M . SE 7 7 7 7 7 . TR. NE 0 0 0 0 0 E . AV. 1 1 1 1 1 T . LO. . PC. Y M E D. S T E. I R. S S S S S I O O E E O E E O o E O O O O U. N N Y Y N Y Y N N Y N N N N Y Q T B E. N Y R. R E A M M DU E S O. SN. G . TI 4 . NN. 0 0 0 0 0 0E 0 0 0 1 0 0 0 0 A N . AI N A . LA 0 I E 2 N L . PM 5 D N P E O I A R. R I D e N F 0 O l M O C I I b I D a T F 0 A T C O 1 R S A . TD. E A E . NE. F E I . EI l& 1E 1 l 1 )O 1M 1 1 1 1 1 1 1 0 H 0 0 0 0 0 0 0 0 0 0 0 0 0 N CE L 0C 0. 0 0 0 0E 0Y 0 0 9 0 0 0 0 T P 1S 1P 1 1 1 1C 1L 1 1 9 1 1 1 1 5 O.RM. (O lP ( ( 1 (N 1E ( ( ( ( ( ( ( F I. EO A N E T S 5 O T.PC. C O S A S N S O I E R M O I S A. T T T R U D I U T T N. C S P C I T E M S U C C T A A M I N D E A A C T L D. E R A E P R C I Y S E L A R S E O I F P.SE. T P T T T F I T MTT NE 7N 7 7A 7M 0H 7E 7 7 7I 6D 7 0 8 1P E I AL 0I 0Y 0D 0A 5C 0D 0S 0 0D 0O 5 5 2 I 1 1C 1 1E E 1 1N 1 1O 1M R LP. PM. N L T O O M T F O E L T I T A C. S G A T E N R E R C S A L O I T T N C W U M S M I T M G N N A I E D E 8 S S C R T E I E O E F I E L 0 U / A M M M I V N P T 8 E T L L I E O I I D E C M 9 A R E. T C D R A A E O R S I 7 T L L. R A A O T T D M S E L SB. O 7F 7R 7E 7N 0N 7I 7 7-7- 7-7A 0 5V 1A TA. N 0 0G 0T 0O 5O 0V 0-0 0 0 5 5Y 2E U NC . AI S 1T 1P C 1O 1 1Y 1Y 1Y T L N . LL R U 1M 1C R T T T 9 I A PP. O E E P T I I I 0 L W M P S P D D I L L L I O A. S P I I N I I I 9 S L T E U S S S S O B B B 7 A P N S S S T T M A A A R P M D E E U U T T T T E I O E Y N N O D I N I 1 I 5 P R R R C D D N O B 8 R 0 O T P . A N E E T T O I A A A . P E R R N N M T H M H 9 E G A A A A A 7 R R P P L L I M M M S S S P 1E E E 1O 2O 1D 2D 1O 2O 3O N N N N M M R R .O .O A A .O O O I I I I C

2. P 1C 1C 3R 3R

4. R

a. R T 0T 7T 0T Y 2E 1P E.

T E 1E 1E

2. L E

N 1E 2E

2. D E 1Y 1Y 3T 3T 3L 3L 36 L

.L .L I E D D R R A N O .u 0 1L 1L 1L 1L . G AA AA AA DA DA D. L D. A DR ER DR .U .U .U .U A R R R R M M L T T T R. B M. B R. B K, B gE IG IG IG II II IP IP IN IN IN M IP IP IP IR IR IN IN IO IO IO IE IE IE IE E IU IU IU IP IP II II IC IC IC II II II II l l '\\! lli;jl ll l l!1li1llI

I

,l

$AFETY ISSUE NANAGEMENT SYSTEM STATUS OF TMI ACTION PLAN - SUpeuRY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PE R CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPP! FED COMPLETED II.R.I.21 1 I (1001 0 NO IE BULLETINS - AUTO SO AllTICIPATORY REACTOR TRIP II.R.1.22 14 14 (100] O NO IE BULLETINS - AUX. NEAT REM SYSTM PROC. II.R.1.23 14 14 (1001 0 NG IE BULLETINS - RV LEVE

L. PROCEDURE

S II.M.1.5 59 50 (ISO) 0 NO IE BULLETINS. REVIEW ESF WALVES II E 2.10 F 7 (ISO) 0 YES F F 7 (1993 y ORDERS ON 86W PLANTS - SAFETY-GRADE TRIP !! K 2.11 7 7 11001 0 YES 7 7 7 (109) ORDERS ON 84W PLANTS - OPERATOR TRAINING II R 2.13 70 78 (100) 9 NO ORLERS ON 84W PLANTS - TNERMAL DECNAMICAL REPORT (CE & W PLANTS ALS0) it K 2.14 7 7 (1001 0 NO ORDERS ON 84W PLANTS - LIFT FREQUENCY OF PORV'S & SV's it R 2.1S 7 7 (1001 0 NO ORDERS 0W 84W PLANTS - EFFECTS OF SLUG FLOW IT M.2.16 7 7 (1991 8 NO ORDERS 04 84W PLANTS - RCP SEAL DAMROE II.K.2.17 72 72 (1991 9 NO ORDERS ON 88W PLANTS - VOIDINS IN RCS (CE & W PLANTS A* S0) it K.2.19 7 7 (1993 0 NO E!!ICHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCETHIt0UGet STM OENERATOR II.M.2.2 7 7 (190) 0 NO ORDERS 04 94W PLANTS - PROCEDURES TO CONTROL AFW IND OF ICS tt.R 2.20 7 7 (1991 e NO ORDERS ON 84W PLANTS - SYSTEM RESPONSE TO S8 LOCA II K.2.8 7 7 (190) 0 YES F S 8 ('1991 ORDERS On 84W PLANTS - UPORADE AFW SYSTEM TetHe 2.4 l

5AFETY I5 SUE MANA0EMENT SYSTEM STATUS OF TMI ACTION PLAN - SUDMARY BY ITEM IMrLEME NT ATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED 11 M ?9 7 7 11001 0 YES 7 7 7 (100) ORDERS 04 B&W PLANTS - FEMA 04 ICS II E 3 1.A 72 72 (100) C NO B&O TASM F0&CE - AUTOMATIC PORY ISOLATION DESION IT M 318 72 T7 (100) 0 YES 72 82 62 (100.i FINAL RECo*MENDATIONS.8&O TA$P. FORCE - AUTO PORY ISO TEST / INSTALL II K 3 10 45 45 11001 0 YES 45 41 41 flool B&O TASM FORCE - PROPOSED ANTICIPATORY TRIP MODIFICATIONS OTS FORCE. JUSTIFY 1 E OF CERTAIN PORY II.M 3.12.A SS 50 (1001 0 NO 8&O TASM FORCE. ANTICIPAYORY TRIP 04 TURBINE TRIP PROPOSED MODS II.M 3.12.8 56 50 11001 0 YES 50 48 48 (100) 840 TASM FORCE - ANTICIPATORY TRIP ON TUR8INE TRIP INSTALL MOOS. II.M.3.13.A 31 31 (1001 8 NO B&O TASM FORCE. MPCI & RCIC SYSTEM INITIATION LEVELS ANALYSIS II.M.3.13.8 31 31 (IC*: 0 YES 31 31 31 (1999 B&O TASM FORCE. MFCI & RCIC INITIATION LEVELS M001FIC 7104 II.M.3.14 8 4 (100) e YES S 5 5 (2001 840 TASM FORCE - ISO COISENSER ISOLATION ON HIGH RAO II.M.3.15 31 31 (190) 0 YES 31 31 31 IIPO) 8&O TASM FORCE - MODIFY leCI & RCIC SRM DETECTION CIRCUITRY II.M.3.18.A 35 35 (104) 0 NO B&O TASM FORCE - CMALLENSE & FAILURE OF RELIEF VALVES STUDY II.M.3.18.8 35 35 (1991 8 YES 35 35 35 (1991 8&O TASM FORCE - CMALLENSE & FAILURE OF RELIEF VALVES MODIFICATIONS !! R.3.17 93 93 (109) 0 NO 840 TASM FORCE - ECC SYSTEM OUTAGES II.M.3.18.A 34 34 (1001 0 NO 840 TASM FORCE - ADS ACTUATION ST12Y Telde 2.4

SAFETY ISSUE MANAGEMEN f SYSTEM STATUS OF TMI ACTION PLAN - SUP94ARY BY ITEM IMPLEME NTATION VERIFICATION PLANTS PLANTS PE R CE N! PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLE TED REMAINING REOUIRED COVERED REQUIRED COMPLETED COMPLETED II M 3.18 B 34 34 11001 0 NO B&O TASM FORCE - ADS ACTUATION PROPOSED MODIFICATIONS II.R 3 18.C 34 34 11001 0 YES 34 33 33 (1001 B&O TASK FORCE - ADS ACTUATION MODIFICATIONS II R 3.19 3 3 (1001 0 YES 3 3 3 (100) B&O TASM FORCE - INTERLOCK RECIRCULATORY PUMP MODIFICATIONS II M 32 70 70 (1001 0 NO B&O TASK FORCE - REPORT 04 PONV FAILURES e II.R 3.20 1 1 (1001 0 YES 1 1 1 (1005 h3 540 TASK FORCE - LOSS OF SVC 1 DATER AT BRP N II K 3.21 A 35 3S (1001 0 NO B&O TASM FORCE - RESTART OF CSS & LPCI LOGIC DESIGN II M 3.21.8 35 35 (1001 0 YES 35 33 33 (1801 B&O TASK FORCE - RESTART OF CSS & LPCI LOGIC DESIGN MODIFICATIONS II.M 3.22.A 39 30 (1001 0 NO B&O TASM FORCE. RCIC SUCTION VERIFICATION PROCEDURES II.M.3.22 8 30 30 (1001 0 NO 840 TASK FORCE - RCIC SUCTION MODIFICATIONS II K.3 24 32 32 (1001 0 YES 32 32 32 1100) 840 TASK FORCE - SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER II.M.3.25 A 100 100 (IODI O NO B&O TASK FORCE - POWER ON PUMP SEALS PROPOSED MODIFICATIONS IT.K.3.25 8 99 99 (1001 0 YES 99 95 95 (1001 B&O TASM FORCE - POWER ON PUMP SEALS MODIFICATIONS II.M.3 27 35 35 (1001 0 YES 35 35 35 (100) B&O TASM FDPCE - COPMON REFERENCE LEVEL FOR BWRS II K.3.28 35 35 (2001 0 YES 35 34 34 (100) B&O TASK FORCE - OUALIFICATION OF ADS ACCUMULATORS II.M.3.29 6 8 (1001 0 NO B&O TASM FORCE. PERFORMANCE OF ISOLATION CONDENSERS Table 2.4

)il\\ll jfl i -l1l il i f l TD. NE.. ) I 1 ) .ET 0 9 9 .CE. 0 5 9 0 L 1 9 1 1 P. ( ( ( 1 .PM. .EO .PC D. E ST .TE. .NL. S 9 0 4 .AP. S 2 5 3 .LM. .PO C N. O. I. D. T SE.. A.TR. C.NI. 6 1 G 4 I.AU. 9 2 S 3 F.LQ I.PE R R E. V D. M SE 7 .TR 2 1 8 9 .NE. E 7 2 1 .AV. .LO. T .PC. S Y M D.. E S T E. S S S S I R.O O 0 O O O 0 O O E E O E O E I.N N N N W N N N N Y Y N Y N Y U. Y Q T B R E N Y R E A 99 M PU E S G. .SN. 4 .TI G NN.0 0 0 0 8 e 9 0 e 9 0 9 0 0 0 2 A N .AI . LA. A PM. e N L P E. W R A t N a H O T I T C S . S .TD. N S A .NE.1G E 1 1 1 l l 1 3 10 1 3s 1E 1 1N E 1 .ET I 0 0 0 e eE 9 9 91 9 9o 9I 0 0A 0 .CE 0N U M L 0L 0 0 t tR 9 9 9Y 9 9A 9T 0 0L 0 P.9E T 1E 1 1 i iU 1 1 1A 1 1 1I 1 1P 1 N.RM.1L S ( (F (L ( t ( (L (D ( ( t tL ( ( 1C O.EO A O I I O I M F S O T.PC H M A F S A I C F T I S N A R I S A A N D N O S G U T. D C E A O O I O O N T A E. N O N L T M I T R R M A L O S G L T A P P E D. I E N U D A V N T Y S L . S 8 T S I S E C I G O W P SE. E A Y 6 S N S I T N I E M.TT. T NE 7 7C 7L 74 5 4 5O 2O 2F 1C 7I eT 7I 7 I AL 7R0U 0F 0I 4A 0 3M 3 3C 7P 7I 2A N SA 9V 9 E 1O 1F 1N 1t T O D E C 1E 1 .LP.1L I I A S I S R O L P I R PM. O A E T W R P M A O F F A C. F N S W R T C U I N I U E F T A S S N V D G R V L J C N W R R O I E R T E P M P P M O M S T I U S M E P 0 C C P E N O L T S W 9 G R O R D E D E. E I I N S F T F E C N L. V R D M W A F F O L M SB. S O O T R O S O G R L O T 7F 7M 7E 7E 1T 4T 5N 2 2 1O 7N tO 7O 7R .TA.7 6G 0 9 0D 0C 3 3 3R 7P 7P 2I O SR 0R 0O .NC.1N 1E 1A 1 1N E S E I R I T 1 1P .AI I L C A A T E C t R P T N L P .LL.. T U O C I A S N f T A C O U .PP. P R D L O L W Y O S t C R S p A. O E L O L L C 9 S E l T P M 8 A A T T C A D N L B E C S O V N F U U R V I O A R S S C E A S A A U E P C C O I T S D N S E H . E E E E E E E I E E R E E L C . C C C C C C C L C C E C C I E . R R R R R R R R R T R R A T O O O O O O O O O A O O T A. F

9. F C. F

. O F F F T A.F 5.F W F F E M.. F 7 D 2 0 0 0 1 4 5 6 E.3E 3K M M K E E E M Y K K S 3

3. S

3. S 3.S

4. S

4. E S. S

5. S

5. F

7. S

9. S T

S S1 61 S S I.3A A A A A A N A A I A A O 0.

3. T

3. T 3.T

3. T

3. O

3. T

3. T 3.T 3A F.1 F. A.

T T R.E M. 0 K. 0 AD AI N P R M. 0 0 K. O RO N.4 K. S M.t M.S M.0 e I ID I4 I4 P PI IM II I I IE I4 IM IM !6 IM Ia . I4 I4 I5 I9 MI MI I !9 IW IR I9 . I8 IB

he*

3 l

SAFETY I S 5 tl E MANAGEMENT SYSTEM STATtrJ OF TMI ACTION PLAN - SUPMARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED MPA.F064 107 107 (100) 0 YES 107 48 48 (100) III.A.1.2 OPERATIONAL SUPP0kT CENTER MPA.F065 107 107 (100] O YES 107 33 33 (100) III.A.1.2 EMERGENCY OPERATIONS FACILITY MPA-F071 107 100 (93 1 7 NO I.D.1.2 DETAILED COMTROL ROOM REVIEW (FDLLOWUP TO F-8) .ro 1 Table 2.4 m

2.5 Conclusions After a detailed review of the implementation and verification status of the TMl Action Plan requirements at alllicensed plants, the NRC staff has concluded the following: I e Progress has been made in the implementation of TMI Action Plan requirements l at all licensed plants. e Licensees continue to make progress toward implementing the remaining iequirements. The schedules currently proposed by licensees for completing i the remaining items are acceptable and are within the timeframes given to the Commission and to Congress. l c I e The NRC closure process for TMI Action Plan items ensures continued adequate protection of the public health and safety. The NRC staff will maintain close watch over the implementation actions and i schedules proposed by licensees to ensure that the 11 TMI requirements that remain to be implemented are completed in accordance with regulatory requirements. l t I.

3 UNRESOLVED SAFETY ISSUES This section presents the overall status of implementation and verification of the requirements imposed following the resolution of USis. 3.1 Imolementation Status Licensees achieve implementation of USl items either by incorporating corrections into the plant design before licensing or by making the modifications necessary to meet requirements at licensed plants. The information presented here includes all USl items related to the 107 licensed plants considered in this report. Approximately 94 percent of the USl items have been implemented at licensed plants. Of the 1,751 applicable items,1,646 have been completed and only 105 remain open from an implementation standpoint. On average, each plant has approximately one remaining item to implement. No plant has more than three remaining items. Figure 3.1 presents the overall status of, and progress on, USis. Of the 107 licensed plants,41 have fully implemented all applicable USIs. Table 3.1 lists the number of unimplemented USl items by plant. Appendix B lists the unimplemented USI items by issue and projected implementation dates. USIs A-44, A-46, and A-47 account for 97 percent of the 105 unimplemented items. Figure 3.2 summarizes the implementation status of these issues. These three USIs are in varying stages of NRC review and licensee implementation, as described below.

A-44 Station Blackout (A022)

The station blackout rule was issued in July 1988. According to the rule, licensees are required to implement their proposed modifications (hardware and procedural) within 2 years of NRC notification approving the licensee's approach. The staff has completed all of the safety evaluation reviews of licensee responses. About half of the plants have proposed major hardware modifications, while the remaining plants are expected to implement minor hardware and procedure modifications. About 56 percent of the sites have already implemented modifications as of December 31,1993, and the staff expects that an additional 34 percent of the sites will complete implementation of the station blackout rule by the end of 1994. Tl 2515/120 was issued on September 24,1993, and pilot inspections were performed at 8 sites, involving all 5 regions. This completed the staff's goal to selectively inspect implementation. Unresolved Safety issues implementation Status at Licensed Plants 2000 - 1500 - t:: d 1000 - 1751 1646 F-500 - 0 i i Applicable implemented Unimplemented Figure 3.1 t 34-

Summary of Unimolemented USI Items by Plant items items items PLANT Remaining PLANT Remaining PLANT Romeining Arkansas 1 2 Hatch 1 2 Prairie Island 1 1 Arkansas 2 3 Hatch 2 2 Prairie Island 2 1 Beaver Valley 1 1 Indian Pt 2 1 Quad Cities 1 3 Big Rock Pt 1 2 indian Pt 3 2 Quad Cities 2 2 Browns Ferry 2 1 Kewaunee 1 Robinson 2 1 Brunswick 1 1 Millstone 1 1 Salem 1 1 Brunswick 2 1 Millstone 2 2 Salem 2 1 Calvert Cliffs 1 3 Monticello 2 San Onofre 2 2 Calvert Cliffs 2 3 Mine Mile Pt 1 1 San Onofre 3 2 Cook 1 1 North Anna 1 2 Sequoyah 1 1 Cook 2 1 North Anna 2 2 Sequoyah 2 1 Cooper Station 2 Oconee 1 1 St. Lucie 1 1 Crystal River 3 1 Oconee 2 1 Surry 1 2 Davis-Besse 1 1 Oconee 3 1 Surry 2 2 6 Dresden 2 2 Oyster Creek 1 2 Three Mlle Island 1 1 m Dresden 3 3 Palisades 2 Turkey Pt 3 1 Duane Arnold 1 Palo Verde 2 1 Turkey Pt 4 1 Farley 1 1 Peach Bottom 2 3 Vermont Yankee 1 1 Fitzpatrick 2 Peach Bottom 3 3 Washington Nuclear 2 1 Ft Calhoun 1 2 Pilgrim 1 2 Waterford 3 2 Ginna 2 Point Beach 1 1 Zion 1 1 Haddam Neck 3 Point Beach 2 1 Zion 2 1 Table 3.1

Summary of Three Unimplzm::nted USls 120-- (107) (107) 100-(s3) 80 -- I a: 60 -- (se) ? 40 - g., (to) ( 0-1 I 1 A-44 A-46 Seismic A-47 Safety Station Qualification of implications of Blackout Equipment - Control l Legend in @mting Mants Systems E Applicable Plants O mplemented Plants i E Unimplemented Plants Figure 3.2 ... - ~ 1

e A-46 Seismic Qualification of Eauioment in Ooeratina Plants (8105) 1 The Generic Implementation Procedure, Revision 2 (GIP-2), was developed by the Seismic Qualification Utility Group (SQUG) for implementation of USI A-46. On May 22,1992, the NRC staff issued its Supplemental Safety Evaluation Report (SSER 2) identifying the conditions under which the GIP-2 resolution is acceptable. Each licensee was required to submit its schedule for implementing the resolution by September 19,1992. Most licensees have committed to use the GIP-2 as supplemented and clarified by SSER 2 and will provide their seismic evaluations for staff review in 1995. Florida Power Corporation (for Crystal River) and Florida Power and Light (for St. Lucie 1 and Turkey Point) are implementing plant-specific resolutions. In addition, by letter dated August 28, 1991, from Dr. T.E. Murley, the licensee for Maine Yankee was informed it need not respond to A-46. e A-47 Safetv Imolications of Control Svstems (B113) The primary focus of the resolution of this USI is to provide a mechanism to trip the main feedwater pumps when a high water level occurs in the reactor vessel or steam generators. In 1990, the staff reviewed the licensees' responses to Generic Letter 89-19 and determined that: - The Westinghouse pressurized-water reactors (PWRs) have implemented the GL recommendations in their designs. However, some facilities did not have the technical specifications for operability of instrumentation. The boiling water reactors (BWRs) (except Oyster Creek and Big Rock Point) and the Combustion Engineering (CE) PWRs (except Palo Verde) concluded that the modifications recommended in the GL are not cost beneficial. The staff has agreed with the BWR Owners Group justification that no further modifications to the existing reactor vessel overfill protection system are necessary. Letters to individual BWR licensees requesting their commitment to the BWROG resolution, and submittal of appropriate technical specification amendments, are being prepared. The staff is continuing its review of the CE Owners Group justification as it relates to assumptions on steam generator tube rupture probability. Review of the Babcock & Wilcox (B&W) plants is continuing on a plant-specific basis because the B&W Owners Group has not taken a position on this issue. i -3 7- )

3.2 Verification Status For generic items such as USIs, NRR issues Tis, when appropriate, to specify which requirements are to be verified by the NRC after licensees have implemented the corrective actions specified in the USI resolution. The NRC performs these inspections, consistent with other inspection priorities, to verify proper implementation of the requirements. Verification is not considered complete until the required inspection is conducted in accordance with the TI, and an inspection report has been issued documenting that requirements have been adequately satisfied by the licensee. On occasion, there may be issues for which the requirements specified in the Tl for safety verification inspection are completed before total implementation of all aspects of the issue's resolution by the licensee. Six Tis have been issued to provide guidance for the field verification of licensee implementation. The Tl designations and the corresponding USIs are listed below. Tl 2500/019 A-26 Reactor Vessel Pressure Transient Protection Tl 2500/020 A-9 Anticipated Transient Without Scram Tl 2515/076 A-24 Qualification of Class 1E Safety-Related Equipment Tl 2515/085 A-7 Mark I Long-Term Program, NUREG-0661, Supplement 1 Tl 2515/120 A-44 Station Blackout Tl 2515/124 A-46 Seismic Qualification of Equipment in Operating Plants (B105) Ternporary Instruction (TI) 2515/124, Seismic Qualification of Equipment in Operating Plants (B105), was issued August 25,1994. Table 3.2 illustrates the items remaining to be verified for these six USis. Table 3.3 includes a summary of the verification status for each plant. Of the 453 items requiring NRC verification,313 Items (71 percent) have been completed. o . L

Summary of USI Items Requiring Verification Plants Plants Plants USI Covered Reauired Verified A-7 Mark I Long-Term Program 22 22 22 A-9 Anticipated Transient Without 107 107 96 Scram A-24 Qualification of Class 1E Safety-107 107 107 Related Equipment A-26 Reactor Vessel Pressure Transient 72 72 66 Protection 107 81* 22 A-44 Station Blackout 64 64 0 A-46 Seismic Qualification of Equipment in Operating Plants NOTE: Covered Plants are those for which USls are applicable Plants Required are those plants requiring field verification. Plants covered but for which field verifcation is not necessary have implemented the reeoivtion in a manner not requinng plant hardware changes

VenTeation done by selectively inspecting implamentation Table 3.2

i j

l j i l 3.3 Status by Plant Table 3.3 summarizes information on the status of implementation and verification of USis at all licensed plants. For each plant, the table shows the total number of applicable items, the number and percentage of items implemented, and the number of items remaining to be implemented. For those USis that require the NRC to verify implementation actions, the table shows the number of items covered by a Tl at each plant, the number of items requiring verification, and the number and percentage of items completed. 1 Forty-one plants have completed all applicable USis. Eight plants have 3 items remaining to be implemented,23 plants have 2 items remaining to be implemented, and 35 plants have one item remaining to be implemented. Six USIs require inspection to verify that implementing actions have been completed. Of the 107 plants,102 have completed at least 50 percent of the applicable USls requiring verification. For the remaining 5 plants, NRC verification is complete for 2 of the 6 USIs that are applicable at those plants. Appendix B lists the unimplemented USI items by issue and gives the projected implementation date, where applicable. 4 b A

SAFE 7Y ISSUE MANAGEMENT SYSt EM STATUS OF USI PLANTS - SUDO4ARY BY UNIT IMPLEMENTATION VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PER CENT UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQUIRED COMPLETED COMPLETED ARKANSAS 1 16 14 (87 1 2 5 5 3 (59 ARKANSAS 2 16 13 (81 ) 3 5 5 3 (59 i BEAVER VALLEY 1 16 15 (93 ) 1 5 5 4 l 79 BEAVER VALLEY 2 15 15 (100) 0 4 4 4 100 BIG RDCK POINT 1 14 12 (85 1 2 4 4 2 i 50 BRAIDWOOD 1 15 15 (100) 0 4 4 3 (75 I BRAIDWOOD 2 15 15 (100 0 4 4 3 (75 i BROWNS FERRY 2 18 17 (94 1 5 5 3 (59 I BRUNSWICK 1 18 17 (94 1 5 5 3 (59 BRUNSWICK 2 18 17 (94 ) 1 5 5 3 (59 BYRON 1 16 16 (100) 0 4 4 3 (75 BYROM 2 15 15 (100) 0 4 4 3 (75 1 ,g CALLAWAY 1 16 16 (1001 0 4 4 3 (75 t n3 CALVERT CLIFFS 1 16 13 (81 3 5 4 3 (75 i CALVERT CLIFFS 2 16 13 (81 3 5 4 3 1 75 e CATAWBA 1 16 18 (100 0 4 4 4 1 100 CATAWBA 2 16 16 (100) C 4 4 4 1 100) CLINTON 1 15 15 (100) 0 3 3 2 1 66 i COMANCHE PEAK 1 15 15 (100) 0 4 4 3 (75 i COMANCHE PEAK 2 16 16 (100) 0 4 4 2 (50 t COOK 1 17 16 (94 ) 1 5 5 3 (59 COOK 2 17 16 (94 ) 1 5 5 3 (59 COOPER STATION 18 16 (88 ) 2 5 5 3 (59 f CRYSTAL RIVER 3 16 15 (93 1 1 5 5 4 (79 I DAVIS-8 ESSE I 16 15 (93 ) 1 5 5 4 (79 ) DIABLO CANYON 1 16 16 (100) 0 4 4 3 (75 ) DIABLO CANYON 2 15 15 (100) 0 4 4 3 (75 ) DRESDEN 2 18 16 I88 ) 2 5 5 3 (59 p DRESDEN 3 18 15 i 83 ) 3 5 5 3 (59 ) DUANE ARNOLD 18 17 l 94 ) 1 5 5 3 (59 ) FARLEY 1 16 15 1 93 3 1 5 5 4 (79 ) FARLEY 2 16 16 (100) 0 4-4 4 (100l FERMI 2 16 16 (100) 0 4 4 3 (75 i FITZPATRICK 18 16 (88 ) 2 5 4 3 (75 i FORT CALHOUN 1 16 14 (87 ) 2 5 5 3 (59 I GINNA 16 14 1 87 ) 2 5 4 3 (75 I GRAND GULF 1 16 16 l 100) 0 3 3 3 (100) HADDAM NECK 18 15 i 53 ) 3 5 4 3 (75 ) HARRIS 1 16 16 l 100) 0 4 4 4 (100) >mTCH I 18 16 1 88 1 2 5 5 3 (59 ) ( 10s l. HATCH 2 18 16 I 88 2 5 5 3 (59 ) HOPE CREEK 1 17 17 0 4 3 3 (100) INDIAN POINT 2 16 15 93 1 5 4 3 75 ) INDIAN POINT 3 16 14 87 2 5 4 3 75 ) Table 3.3

SAFETY ISSUE MANAGEMEN 7 SYSTEM STATUS OF USI PLANTS - SUPNARY BY UNIT IMPLEMENTATIDN VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PER CENT UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQUIRED COMPLETED COMPLEIED KEWAUNEE 16 15 (93 ) 1 5 5 -3 (59 ) LASALLE 1 17 17 (100) 0 3 3 2 (66 ) LASALLE 2 16 16 (100) 0 3 3 2 (66 ) LIME RICK 1 16 16 (100) 0 3 2 2 (100) LIMERICK 2 16 16 (100) 0 3 2 2 (100) MAINE YANKEE 16 16 (100) 0 5 4 3 (75 ) MCGUIRE 1 18 18 (100) 0 5 5 3 (59 1 MCGUIRE 2 18 18 (100) 0 5 5 3 (59 ) MILLSTONE 1 19 18 (94 ) 1 5 4 3 (75 ) MILLSTONE 2 16 14 (87 ) 2 5 4 3 (75 ) MILLSTONE 3 16 16 (100) 0 4 3 3 (100) MONTICELLO 18 16 (88 ) 2 5 5 3 (59 ) MIWE MILE POINT 1 18 17 (94 ) 1 5 4 3 (75 ) A MIME MILE POINT 2 'S 16 (1001 0 3 2 2 (100) Ca3 NORTH ANNA 1 .6 14 (87 ) 2 5 5 3 (59 ) NORTH ANNA 2 17 15 (88 ) 2 5 5 3 (59 ) OCONEE 1 16 15 (93 ) 1 5 5 1 (19 ) OCONEE 2 16 15 (93 ) 1 5 5 1 (19 ) .DCOMEE 3 16 15 (93 ) 1 5 5 1 (19 ) OYSTER CREEK 1 18 16 (88 ) 2 5 4 3 (75 ) PALISADES 16 14 (87 ) 2 5 5 3 159 ) PALO VERDE 1 15 15 (100) 0 4 4 3 (75 ) PALO VERDE 2 15 14 (93 1 1 4 4 3 (75 ) PALO VERDE 3 15 15 (100) 0 4 4 3 (75 ) PEACH BOTTOM 2 18 15 (83 ) 3 5 4 3 (75 ) PEACH BOTTOM 3 18 15 (83 ) 3 5 4 3 (75 ) PERRY 1 15 15 (100) 0 3 3 2 (66 I PILGRIM 1 18 16 (88 ) 2 5 5 4 (79 I POINT BEACH 1 16 15 (93 1 1 5 5 3 159 l P POINT BEACH 2 16 15 (93 ) 1 5 5 3 59 I PRAIRIE ISLAND 1 16 15 (93 ) 1 5 5 3 1 59 l PRAIRIE ISLAND 2 16 15 (93 ) 1 5 5 3 (59 i QUAD CITIES 1 18 15 (83 ) 3 5 5 3 (59 ) OUAD CITIES 2 18 16 (88 ) 2 5 5 3 (59 ) RIVER BEND 1 15 15 (100 0 3 3 2 (66 ) ROBINSON 2 16 15 193 l 1 5 5 4 (79 ) 1 5 4 3 (75 ) SALEM 1 16 15 l 93 i SALEM 2 17 16 i 94 l 1 5 4 3 (75 ) SAN ONOFRE 2 16 14 I 87 ) 2 4 4 3 (75 ) SAN ONOFRE 3 16 14 i 87 ) 2 4 4 3 (75 ) SEABROOK 1 15 15 (100) 0 4 3 3 (100) SEQUOYAH 1 18 17 (94 l 1 5 5 2 (39 ) SEQUOYAH 2 28 17 (94 ) 1 5 5 2 (39 ) SOUTH TEXAS 1 IS 15 (1001 0 4 4 3 (75 ) Table 3.3

5AFE7Y ISSUE MANAGEMENT SYSTEM STATUS OF USI PLANTS - SupW4ARY BY UNIT IMPLEMENTATION VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PER ' CENT UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQUIRED COMPLETED COMPLETED i SOUTH TEXAS 2 15 15 (1001 0 4 4 3 (75 ) ST LUCIE 1 16 15 (93 1 1 5 5 3 1 59 ) ST LUCIE 2 16 16 (100) 0 4 4 3 l 75 1 SUP91E R 1 16 16 (100) 0 4 4 3 1 75 ) l SURRY 1 16 14 (87 ) 2 5 5 3 (59 ) SURRY 2 16 14 (87 ) 2 5 5 3 (59 ) SUSCUEHANNA 1 17 17 (100) 0 3 2 2 (100) SUSOUEHANNA 2 16 16 (100) 0 3 2 2 (200) THREE MILE ISLAND 1 16 15 (93 ) 1 5 4 3 (75 ) h TURMEY POINT 3 16 15 (93 ) 1 5 5 4 (79 l' TURMEY POINT 4 16 15 (93 ) 1 5 5 4 (79 ) VERMONT YANKEE 1 18 17 (94 ) 1 5 4 3 (75 l l A VOGTLE 1 15 15 (1001 0 4 4 3 (75 i I VOGTLE 2 16 16 (100 1 0 4 4 3 175 i l WASHINGTON NUCLEAR 2 16 15 (93 1 1 3 3 2 (66 i l WATERFORD 3 15 13 (86 2 4 4 3 (75 l WOLF CREEK 1 16 16 (100 t 0 4 4 3 (75 ) l ZION 1 16 15 (93 1 5 5 3 (59 ) ZION 2 16 15 (93 1 5 5 3 (59 ) TOTALS / AVERAGES 1751 1646 94 105 479 453 313 71-i 1 l Table 3.3 i l c.

3.4 Status bv Issue Table 3.t. presents summary information on the status of implementation and verification of each USl. For each issue, the table shows the number of applicable plants, the number and percentage of plants that have completed implementation, and the number of plants remaining to complete implementation. For those issues requiring NRC verification of corrective actions, the table shows the number of plants covered by the issue, the number of plants at which verification is required, and the number and pe:::entage of plants that have completed verification. Of the 27 USIs, 22 have been fully implemented. (USIs A-3, A-4, and A-5 relate to steam generator tube integrity for the three major PWR vendors and are considered separate issues.) Three USis account for 97 percent of the unimplemented items: A-44, Station Blackout, with 24 plants remaining to complete implementation; A-46, Seismic Qualification of Equipment in Operating Plants, with 59 plants remaining to complete implementation; and A-47, Safety implication of Control Systems, with 19 plants remaining to complete implementation. These three, largely unimplemented, USIs are in varying stages of NRC review and licensee implementation, as discussed in Section 3.1 of this report. The remaining USIs have 1 or 2 plants remaining to complete implementation. NRC inspection to verify licensee implementation is required for six USIs and is complete for USl A-7, Mark I long-term program, and A-24, Qualification of Class IE Safety-Related Equipment. A-44, Station Blackout and A-46, Seismic Qualification of Equipment in Operating Plants account for 123 of the 140 outstanding verifications. l 1 SAFE 7Y ISSUE MANAGEMEN7 SYSTEM STATUS OF USI PLANTS -

SUMMARY

BY ITEM IMPLEMENTATION VERIFICAT13N PLANTS PLANTS PER CENT PLANTS PLAMTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED A-1 107 107 (100) 0 NO WATER HAMMER A-2 72 72 (100) 0 NO ASYt99E?RIC BLOWDOWN LOADS ON REACTOR PRIMARY COOLANT SYSTEMS A-3, 4 AND S 72 72 (100) 0 NO STEAM GENERATOR TUBE INTEGRITY A-6 21 21 (1001 0 NO MARK I SHORT-TERM PROGRAM A-7 22 22 (1001 0 YES 22 22 22 (100) g MARK I LONG-TERM PROGRAM 9 A-8 8 8 (1001 0 NO MARK II CONTAINMENT POOL DYNAMIC LOADS LONG-TERM PROGRAM A-9 107 105 (98 ) 2 YES 107 107 96 (89 ) ATWS A-10 34 34 (100) 0 NO BWR FEEDWATER N0ZZLE CRACKING A-11 107 107 (1001 0 NO REACTOR VESSEL MATERIALS TOUGHNESS A-17 107 107 (100) 0 NO SYSTEM INTERACTIONS IN NUCLEAR POWER PLANTS A-24 107 107 (1001 0 YES 107 107 107 (100) QUALIFICATION OF CLASS IE SAFETY-RELATED EQUIPMENT A-26 72 72 (1001 0 YES 72 72 66 (91 ) REACTOR VESSEL PRESSURE TRANSIENT PROTECTION A-31 51 50 (98 ) 1 NO RHR SHUTDOWN REQUIREMENTS A-36 (C010) 107 107 (100) 0 NO CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE ONE) A-36 (C015) 75 75 (100) 0 NO CONTROL OF HEAVY LOADS - PHASE II (FOLLOWUP OF MPAR C-10) Table 3.4

SAFETY ISSUE MANAGEMENT SYSTEM STATUS OF USI PLANTS - SUpetARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS -LANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE Cbr4PLE TED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED A-39 34 34 100) 0 NO DETERMINATION OF SRV POOL DYNAMIC LOADS & TEMP. LIM TS FOR BWR CNTMNTS A-40 3 3 (100) 0 NO SEISHIC DESIGN CRITERIA A-42 36 36 (100) 0 NO PIFE CRACKS IN BOILING WATER REACTORS A-43 107 107 (100) 0 NO CONTAINMENT EMERGENCY SUMP PREFORMANCE A-44 107 83 (77 ) 24 YES 107 81" 22 (27 ) g STATION BLACKOUT 7 A-45 107 107 (100) 0 NO SHUTDOWN DECAY HEAT REMOVAL REQUIREMENTS A-46 64 5 (7 ) 59 YES 84 64 0 (0 ) SEISMIC QUALIFICATION OF EQUIPMENT IN OPERATING PLANTS A-47 107 88 (82 ) 19 NO SAFETY IMPLICATION OF CONTROL SYSTEMS A-48 45 45 (100) 0 NO HYDROGEN CONTROL MEASURES AND EFFECTS OF HYDROGEN BURNS A-49 72 72 (100) 0 NO PRESSURIZED THERMAL SHOCK

VerdiCahon done by RL ^.id mopqM2irg Wion i

TatWe 3.4

3.5 Conclusions After a detailed review of the implementation and verification status of the resolution of the 27 USIs, the NRC staff has concluded the following: The NRC closure process for USis ensures continued adequate protection of the e public health and safety. All USIs have been resolved by the NRC, and progress has been made in e implementing and verifying required changes at plants. l Licensees are making adequate progress toward implementing requirements e imposed following the NRC's resolution of USis, and the framework exists to oversee future implementation of delayed items. Although the resolution of USIs involves complex technicalissues and analyses, e it appears that all required implementation items can be completed in accordance with regulatory requirements. I 't -4 9-

i 4 GENERIC SAFETY ISSUES This section presents the overall status of implementation and verification of GSis applicable at the 107 licensed plants. Because each GSI may be traded under different designations, Table 4.1 cross references the GSI and sub-issue number and the SIMS numbers used in the tables and appendices of this report. 4.1 Imolementation Status Licensees achieve implementation of GSI items either by incorporating corrections into the plant design before licensing or by making the modifications necessary te meet the requested actions at licensed plants. The information presented here includes all GSI items related to the 107 licensed plants considerr,d in this report. Approximately 98 percent of the GSI items have been implemented at licensed plants. Of the 2,579 items, 2,516 have been completed and 63 remain open from an implementation standpoint. On average, each plant has 1 item to implement, and no plant has more than 4 remaining items. Figure 4.1 presents the overall status of, and progress on, GSl; Of the 107 licensed plants, 68 have implemented all applicable GSis. Table 4.2 lists the number of unimplemented items by plant. Appendix C lists the unimplemented GSI items by issue and projected implementation dates. Five GSis have not been implemented at a number of plants for which they are applicable; these account for approximately 94 percent of the unimplemented items. Figure 4.2 summarizes the implementation status of these issues. A brief description of each issue follows. e GSI43 Reliability of Air Systems (B1071 In August 1988, the staff issued GL 88-14 to specify the performance of a design and operations verification of instrument air systems and descriptions of licensees' proprams for maintaining proper instrument air quality. The staff gave licensees 6 months in which to confirm that these actions had been accomplished or to commit to perform them during a subsequent outage. Most of the plants that still have this issue open have completed 80 to 90 percent of the significant recommended actions and are awaiting a suitable outage opportunity to complete the final actions. The staff believes that the planned completion schedules do not pose any significant safety risk., L I

GSI Numbers and Corresponding SIMS ltem Numbers SMS MPA ftem Nm faSLMt _Ms SIMS Title 40 40 8065 Safety Concems Associated With Pipe Breaks in BWR Scram System 41 41 8050 BWR Scram Discharge Volume Systems GL-88-14 43 B107 Instrument Air Supply System Problems Affecting Safety-Related Equip. GL-89-13 51 L913 Service Water System Problems Affecting Safety-Related EquWnent 67.3.3 67.3.3 A017 Improved Accident Monitoring 70 70 B114 PORV and Block Valve Rehability 75 (0076) 75, Item 1.1 B076 Item 1.1 - Post-Trip Rever, Program Desenption & Procedures 75 (BOBS) 75, item 1.2 8085 ftem 1.2 - Salem ATWS 1.2 Data Capabilty 75 (B077) 75, item 2.1 B077 Item 2.1 - Equipment Classification & Vendor Interface - RTS Component 75 (8086) 75, item 2.2.1 B086 Item 2.2.1 - Salem ATWS 22 S-R Components l GL-90-03 75, item 2.22 LOO 3 Item 22.2 - Relaxation of Staff Pos in Gen Letter 83-28, item 22 Part 2 75 (B078) 75, items 3.1.1 & 3.12 B078 Items 3.1.1 & 3.1.2 - Post-Maintenance Test Procedures & Vendor Recomm. l 75 (B079) 75, item 3.1.3 B079 Item 3.1.3 - Post-Maintenance Testing - Changes to Tech Specs - RTS Component l 75 (8087) 75, items 3.2.1 & 3.2.2 8087 Items 3.2.1 & 3.22 - Salem ATWS 3.2.1 & 322 S-R Components 75 (B088) 75, item 3.2.3 B088 Item 3.2.3 - Salem ATWS 32.3 T.S. S-R Components) 75 (B080) 75, item 4.1 8080 Item 4.1 - Reactor Trip System Rehabsty - Vendor Related Mods E 75 (8081) 75, items 4.2.1 & 422 B081 Items 4.2.1 & 422 - Preversative Maint Prog for Reactor Trip Breakers 75 (8082) 75, item 4.3 B082 Item 4.3 - Automatic Actuation of Shunt Trip Attach. for West & B&W 75 (8090) 75, item 4.3 B090 Item 4.3 - Salem ATWS 4.3 W and B&W T.S. 75 (8091) 75, item 4.4 8091 Item 4.4 - Sakm ATWS 4.4 B&W Test Procedures 75 (8092) 75, item 4.5.1 8092 Item 4.5.1 - Salem ATWS 4.5.1 Diverse Trip Features 75 (8093) 75, items 4.5.2 & 4.5.3 B093 ftems 4.52 & 4.5.3 - Salem ATWS 4.5.2 & 4.5.3 Test Altematives 86 86 B084 Long Range Plan Deeling With Stress Curics,kni Cracking in BWR Pipmg GL-88-03 93 B098 Resolution of GSI 93, " Steam Bindmg of Auxiliary Feedwater Pumps" 94 94 B115 Additional Low-Term Overpreseure Protection for LWRs GL-88-17 99 L817 Loss of Decay Heat Removal 124 124 S001 Auxiliary Feedwater System Rehabihty GL-80-099 A-13 B107 Technical Spectheation Revision for Snubber Surveillance GL-84-13 A-13 B022 Technical Specification for Snubbers A-16 A-16 D012 Steam Effects on BWR Core Spray Distribution MPA-8023 A-35 B023 Degraded Grid Voltage B-10 B-10 S008 Behavior of BWR MaiklliContamments B-36 B-36 none Dev Desegn, Test & Maint Criteria for Atmo Cleanup Sys Air Filter & Adsorption Ur:its GL-80-014 B-63 B045 LWR Pnmary Coolant System Pressure Isolahon Valvec Table 4.i

1 l l Generic Safety issues implementation Status at Licensed Plants l' 3000 2500 -

1

$ 2000 - E N 1500 - B 1000 - 500 - 0 i Appilcable implemented Unimplemented i Figure 4.1 i l i l 53-

I Summary of Unimolemented GSI Items by Plant items Items items PLANT Remaining PLANT Remaining PLANT Romeining Arkansas 2 2 Fermi 2 1 Nine Mile Pt 1 1 Beaver Valley 1 3 Ginna 4 North Anna 1 2 Beaver Valley 2 2 Haddam Neck 2 North Anna 2 2 Braidwood 1 1 Hatch 1 1 Oyster Creek 1 1 Braidwood 2 1 Hatch 2 1 Palo Verde 2 1 Browns Ferry 2 1 Indian Pt 2 1 Quad Cities 1 1 Calvert Cliffs 1 1 LaSalle 1 1 Quad Cities 2 2 Calvert Cliffs 2 2 LaSalle 2 1 St. Lucie 1 1 Catawba 1 1 Maine Yankee 1 St. Lucie 2 1 Catawba 2 1 McGuire 1 4 Summer 1 3 Cooper Station 1 McGuire 2 4 Surry 1 1 Dresden 2 1 Millstone 1 3 Surry 2 1 Dresden 3 2 Millstone 2 2 Wolf Creek 1 1 TatWe 4.2

Summ:ry cf Fiva Unimplemented GSis 120-- (107) (107) (107) 100 -- (94) 30 g (66) (ss) j 60 -- 40 -- 20 - 3 0 I I I I I I I I I I GL-88-14 GL-89-13 67.3.3 70 94 (8107) (L913) (A017) (B114) (OliS) SIMS Numbers g E Total 05.r+:.Taed E Unimplemented Figure 4.2 l%.

e GSI51 Prooosed Raouirements for Imorovino the Reliability of Ooen-Cvele Service Water Systems (L913) This issue was developed as a result of uncertainties regarding the compliance of service water systems with the regulations. In July 1989, the staff issued l GL 89-13 request ng licensees to take certain actions and establish programs to i ensure continued compliance of their service water systems with the applicable regulations. The staff asked licensees to submit implementation plans and schedules by early 1990. The actions and programs have been implemented at approximately 86 percent of all plants. Temporary Instruction Tl2515/118 was issued on December 29,1992, to assess the licensees' planned or completed 1 actions in response to GL 89-13. The staff considers the status of this GSI ~ acceptable. e GSI 67.3.3 Imoroved Accident Monitorino (A017) [ This issue addresses conformance with RG 1.97, " Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant and Environs 4 l Conditions During and Following an Accident." The staff issued GL 82-33 in l December 1982 to request licensees to submit schedules and details of their plans to implement the provisions of RG 1.97, Revision 2. The licensae responses to this generic letter prompted the staff to issue confirmatory orders in 1985. Because the industry has taken exception to and appealed some of ~ the provisions of RG 1.97, Revision 2, implementation is incomplete at many [ plants. i The issues of Category 1 neutron flux monitoring at BWRs and Cctegory 2 instrumentation to monitor containment sump water temperature at PWRs have t been resolved. The issue of Category 1 neutron flux monitoring at 3 PWRs is i still under review. e GSI70 PORV and Block Valve Reliability (B114) The generic issue involves the evaluation of the reliability of power-operated relief valves (PORVs) and block valves and their safety significance in pressurized water reactors (P'NRs). Traditionally, the PORV and its block valve are provided for plant operational flexibility and for limiting the number of challenges to the safety related function, i.e., one on which the results and conclusions of the safety analysis are based and that invokes the highest level { of quality and construction. t l The Three Mile Island Unit 2 accident focused attention on the reliability of l j PORVs and block valves since the malfunction of the PORV at TMl-2 contributed to the severity of the accident. On other occasions, PORVs have stuck open when called upon to function. Also, there are PORVs in many operating plams that have leakage problems so that the plants must be 56-I

1 i I operated with the upstream block valves in the closed position. The technical specifications governing PORVs on most operating PWRs, which deal with closing the 5 lock valve and removing power, were developed to allow continued plant operation with degraded PORVs, but did not consider the need for the PORVs to perform safety-related functions:

1. Mitigation of the design-basis steam generator tube rupture accident

2. Low-temperature overpressure protection of the reactor vessel during startup and shutdown

3. Plant cooldown in compliance with Branch Technical Position RSB5-1 to SRP 5.4.7, " Residual Heat Removal (RHR) System" In Generic Letter 90-06, " Resolution of Generic issue 70, ' Power-Operated Relief Valve and Block Valve Reliability,' and Generic issue 94, " Additional Low-Temperature Overpressure Protection for Light-Water Reactors,' Pursuant to 10 CFR 50.54(f), " the staff determined that certain upgrades to the quality program, in-service testing and technical specifications represented cost i

justified safety enhancements. The proposed technical specification would require a plant shutdown after 72 hours, if the PORV was declared inoperable for reasons other than excessive leakage. Those PWRs that relied on the PORVs and block valves to perform one or more of the above safety-related functions were requested to adopt the upgraded positions of the generic letter. The generic issue was applicable to those PWR plants that include PORVs and block valves in their design. As of Augus' 1994, the staff has completed its review for 51 plants. Open issues still remain for the remaining 14 plants, o GSI94 Additional Low-Temoerature Overoressure Protection for Llaht-Water Reactors (B115) The generic issue addresses concerns regarding the implementation of the requirements set forth in the resolution of Unresolved Safety issue (USI) A-26, " Reactor Vessel Pressure fransient Protection (Overpressure Protection)." Pressurized water reactor (PWR) licensees implemented procedures to reduce the potential for overpressure events and installed equipment modifications to mitigate such events based on the staff recommendations from the USl A 26 evaluations, under Multi-Plant Action Item B-04 (NUREG-0748). Major overpressurization of the reactor coolant system while at low temperature, if combined with a critical crack in the reactor pressure vessel welds or plate material, could result in a brittle fracture of the pressure vessel. Failure of the pressure vessel could make it impossible to provide adequate coolant to the reactor core and result in major core damage or a core melt accident. Mitigation of overpressure events is provided by either the power-operated relief valves (PORVs) operating in the low-temperature 4 overpressure protection (LTOP) mode or by the relief valves in the residual heat removal systems. Following the resolution of USl A-26, the industry continued to experience overpressure transient events. The continuation of overpressure transient events, and the unavailability of LTOP protection channels, suggested the need to reevaluate the current overpressure protection criteria, or their implementation, to deterrnine whether additional considerations were warranted. In Generic Letter 90-06, " Resolution of Generic Issue 70, ' Power-Operated Relief Valve and Block Valve Reliability,' and Generic issue 94, " Additional Low-Temperature Overpressure Protection for Light-Water Reactors,' Pursuant to 10 CFR 50.54(f), " the staff determined that certain upgrades to the technical specification regarding the availability of PORVs during the LTOP mode were cost-Justified safety enhancements. The generic letter recommended that the technical specification be modified to reduce the unavailability of PORVs during low temperature operations. The generic issue was applicable to Westinghouse and Combustion Engineering plants. As of August 1994, the staff has cornpleted its review for 51 plants. Open issues still remain for 10 plants. 4.2 Mtrjfication Status For generic items such as GSis, NRR issues Tis for those items that need to be verified in the field by the NRC staff after licensees have implemented the actions specified in the GSI resolution. The NRC performs these inspections, consistent with other inspection priorities, to verify proper implementation of the requirements. Verification is not considered complete until the required inspection is conducted in accordance with the Tl and an inspection report has been issued documenting that the requirements have been adequately satisfied by the licensee. On occasion, there may be issues for which the requirements specified in a Tl for safety verification inspection are completed before full implementation of all aspects of the issue's resolution by the licensee. Of the 1,147 items requiring NRC verification, 1,055 (92 percent) have been completed. Eight Tis provide guidance for the field verification of licensee implementation of GSis. Tl designations and the corresponding GSis are provided in Table 4.3. Table 4.4 summarizes the items remaining to be verified. L 1 Temporary instructions for Resolved GSis SIMS Item SIMS Title Il 41 BWR SCRAM DISCHARGE VOLUME SYSTEM 2515/090 67.3.3 IMPROVED ACCIDENT MONITORING 2515/087 75 (B077) ITEM 2.1 - EQUIPMENT CLASSIFICATION & 2515/064 VENDOR INTERFACE - RTS COMPONENT 75 (8078) ITEMS 3.1.1 & 3.1.2 - POST MAINTENANCE 2515/064 TEST PROCEDURES & VENDOR RECOMM. 75 (B079) ITEMS 3.1.3 - POST MAINTENANCE TESTING - 2515/064 CHANGES TO TECH SPECS - RTS COMPONENT l 75 (B080) ITEM 3.1 - REACTOR TRIP SYSTEM RELIABILITY 2515/091 - VENDOR RELATED MODS 75 (8081) ITEMS 4.2.1 & 4.2.2 - PREVENTIVE 2515/064 MAINTENANCE PROGRAM FOR REACTOR TRIP BREAKERS SALEM ATWS 3.2.1 & 3.2.2 S-R COMPONENTS 75 (8086) SALEM ATWS 2.2 S-R COMPONENTS 2515/064 75 (B087) SALEM ATWS 3.2.1 & 3.2.2 S-R COMPONENTS 2515/064 75 (B088) SALEM ATWS 3.2.3 T.S. S-R COMPONENTS 2515/064 75 (B092) SAli.M ATWS 4.5.1 - DIVERSE TRIP FEATURES 2515/064 86 LONG RANGE PLAN DEALING WITH STRESS 2515/089 CORROSION CRACKING IN DWR PIPING GL-88-17 LOSS OF DECAY HEAT REMOVAL 2515/101 2515/103 GL-89-13 SERVICE WATER SYSTEM PROBLEMS 2515/118 AFFECTING SAFETY-RELATED EQUIPMENT Table 4.3 J

Summary of GSI item 3 Requiring Verification films Item Plants Plants Plants Covered Required Verified I 67.3.3 IMPROVED ACCIDENT MONITORING 107 106 94 75 (B000) ITEM 4.1 - REACTOR TRIP SYSTEM 72 72 71 RELIABILITY-VENDOR RELATED MODS GL-88-17 LOSS OF DECAY HEAT REMOVAL 72 72 71 GL-89-13 SERVICE WATER SYSTEM 107 98 20 .8 PROBLEMS AFFECTING SAFETY-I RELATED EQUIPMENT NOTE Plants Covmed are moss for wNeh GSis we e Plants Required are moes plants requmng feed venheshort Plants covered but for wNch field vertication is not m have implemented me resoluton h a memor not regimmg pimrt hanswere changes.. Table 4.4

4.3 Status by Plant l Table 4.5 summarizes the status of implannentation and verification of GSis at all licensed plants. For each plant, the table shows the total number of applicable l items, the number and percentage of items implemented, and the number of items l remaining to be implemented. For those GSis that require NRC to verify implementation of corrective actions, the table shows the number of items covered by the Tis at each plant, the number of items requiring verification, and the number and percentage of items completed. Appendix C lists the unimplemented GSI items by issue and gives projected implementation dates. Of the 107 plants, 68 have completely implemented all GSI items. Thirty three plants have completed implementation actions for all except 1 or 2 GSis, and the remaining 6 plants have 3 to 4 items to implement. Of the 107 plants,26 plants have completed all of the items requiring verification by inspection (in accordance with a TI); 80 plants have completed all but 1 or 2 items requiring verification; and one plant has completed all but 3 items. 61

I } SAFETY ISSUE MANAGEMENT SYSTEN STATUS OF GSI PLANTS. SUBMARY BY UNIT IMPLEMENTATION VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PER CENT UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQUIRED COMPLETED COMPLETED ARKANSAS 1 27 27 (100) 0 12 4 3 (75 1 i ARKANSAS 2 25 23 (91 ) 2 12 4 3 (75 t BEAVER VALLEY 1 26 23 (88 ) 3 12 12 12 (100 BEAVEM VALLEY 2 27 25 (92 1 2 12 4 4-(100 1 i BIG RDCK POINT 1 21 21 (100) 0 11 10 9 (89 BRAIDWOOD 1 27 26 (96 ) 1 12 12 11 (91 BRAIDWOOD 2 27 26 (96 ) 1 12 12 11 (91 BROWNS FERRY 2 21 20 (95 I 1 11 11 10 (90 BRUNSWICK 1 19 19 .(100) 0 11 11 10 (90 BRUNSWICK 2 19 19 (100) 0 11 11 10 (90 I BYROM i 27 27 (1001 0 12 12 11 (91 i i BYROM 2 27 27 (100) 0 12 12 11 191 CALLAWAY 1 26 26 (200) 0 12 12 11 (91 CD CALVERT CLIFFS 1 23 22 (95 ) 1 12 12 12 i 190 I fV CALVE R T CLIFFS 2 23 21 (91 ) 2 12 12 12 1 100 I CATAWBA 1 27 26 (96 1 1 12 12 12 i 100 1 CATAWBA 2 27 26 {96 3 1 12 12 12 i 100 CLINTON 1 21 21 ge00) 0 11 11 10 ' 90 COMANCHE PEAM i 26 26 ( 1C ' O 12 11 11 1 100 l COMANCHE PEAK 2 26 26 (100) 0 12 11 8 1 72 t COOK 1 25 25 (100) 0 12 12 11 i 91 COOK 2 25 25 (100) 0 12 12 11 1 91 i i COOPE R STATION 21 20 (95 ) 1 11 4 3 (75 CRYSTAL RIVER 3 27 27 11003 0 12 12 11 191 i' DIABLO CANYON 1 26 26 (100) 0 12 12 12 1 100 DAVIS-BESSE 1 26 26 (100) 0 12 12 10 83 1 i r DIABLO CANYON 2 26 26 (100) 0 12 12 12 l 100 DRESDEN 2 20 19 (94 ) 1 11 11 9 ! S1 DRESDEN 3 20 18 (89 ) 2 11 11 9 1 91 1 DUANE ARNOLD 21 21 (100) 0 11 11 10 I SS l FARLEY ! 26 26 (1001 0 12 12 12 1 190 1 FARLEY 2 26 26 (100) 0 12 12 12 (199 t FERHI 2 21 20 (95 l 1 11 11 9 '81 1 i l FITZPATRICK 21 21 (1001 0 11 11 10 ' 99 FORT CALHOUN 1 25 25 (1001 0 12 9 8 i 88 GINNA 26 22 (84 l 4 12 12 11 1 91 GRAND GULF 1 21 21 (100) 0 11 11 10 1 90 HADDAM NECK 26 24 (92 ) 2 12 12 11 i 91 1 HARRIS 1 27 27 (100) 0 12 12 11 1 91 1 HATCH 1 21 20 (95 ) 1 11 11 11 1 199 HATCH 2 21 20 195 ) 1 11 11 11 1 109 HOPE CREEK 1 22 22 (100) e 11 3 3 (tee i INDIAN POINT 2 25 24 (95 ) 1 12 12 12 (129 INDIAN POINT 3 26 26 (100) 0 12 12 12 (104 1 i TatHe 4.5

5AFETY ISSUE MANAGEMENT SYSTEM STATUS OF GSI PLANTS - SUPMARY BY UNIT IMPLiMENTATION VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PER CENT UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQUIRED COMPLETED COMPLETED KEWAUNEE 25 25 (1001 0 12 12 II (91 ) LASALLE 1 22 21 (95 1 1 11 11 9 (81 ) LASALLE 2 22 21 (95 1 1 11 11 9 (81 ) LIMERICK 1 20 20 (1001 0 11 3 3 (100) LIVERICK 2 20 20 (100) 0 11 3 3 (100) MAINE TANKEE 24 23 (95 1 1 12 12 11 (91 ) MCGUIRE 1 26 22 (84 1 4 12 1. 11 191 ) MCGUIRE 2 26 22 (84 ) 4 12 12 11 1 91 ) MILLSTONE 1 21 18 (85 ) 3 11 LI 10 1 90 ) ( 200 l1 t91 MILLSTONE 2 24 22 (91 1 2 12 12 11 MILLSTONE 3 27 27 (100) e 12 3 3 MONTICELLO 20 20 1100) C 11 11 10 (90 ) MINE MILE POINT 1 22 21 195 ) 1 11 11 11 (100) NINE MILE POINT 2 22 22 (100) 0 11 4 4 (100) h' NORTH ANNA 1 26 24 (92 ) 2 12 12 11 191 ) NORTH ANNA 2 26 24 (92 ) 2 12 12 11 I 91 I OCONEE 1 26 26 (100) 0 12 12 11 i 91 1 DCONEE 2 26 26 (1001 0 12 12 11 (91 1 DCONEE 3 26 26 (100) 0 12 12 11 (91 OYSTER CREEK 1 22 21 195 1 1 11 11 10 (90 1 PALISADES 24 24 (100) 0 12 12 10 .(83 l PALO VERDE 1 23 23 (100) 0 12 12 11 (91 1 PALO VERDE 2 23 22 (95 ) 1 12 12 11 (91 ) PALO VERDE 3 23 23 (100) 0 12 12 11 (91 ) PEACH BOTTOM 2 21 21 (100) 0 11 11 10 (90 ) PEACH BOTTOM 3 21 21 (1001 0 11 11 10 (90 ) PERRY 1 22 22 1100) 0 11 11 10 (90 PILGRIM 1 21 21 (100l 0 11 11 10 (90 POINT BEACH 1 25 25 (100, 0 12 12 11 (91 POINT BEACH 2 25 25 (100) 0 12 12 11 (91 ) PRAIRIE ISLAND 1 26 26 (100) 0 12 12 11 (91 ) PRAIRIE ISLAND 2 26 26 (100) 0 12 12 11 (91 ) OUAD CITIES 1 21 20 (95 ) 1 11 11 9 (81 ) ouAD CITIES 2 21 19 (90 1 2 11 11 9 (81 1 RIVER BEND 1 20 20 (1001 0 10 3 2 (66 I RD81NSON 2 26 26 (100) 0 12 12 12 (100 i SALEM 1 26 26 (100) 0 12 12 11 (91 l SALEM 2 26 26 (100) 0 12 12 11 (91 SAN ONOFRE 2 24 24 (100) 0 12 12 11 (91 i SAN ONOFRE 3 24 24 (100) 0 12 12 11 191 SEABROOK 1 27 27 (100) 0 12 11 11 (100) SEQUOYAH 1 27 27 (1001 0 12 12 11 191 ) SEQUOYAH 2 27 27 (100) 0 12 12 11 (91 ) SOUTH TEXAS 1 27 27 (100) 0 12 12 11 (91 ) 1 Table 4.5 -.e-- m-mn.--. n-w.,..%, ..--,n-- + ~. < _ ..rw=-<

w e

-.,--,w,e,re .-e-n --s e .a~

$AF ETY ISSUE MANAGEMENT SY STEM STATUS OF GSI PLANTS - SUNMARY BY UNIT IMPLEMENTATION VERIFICATICM I TE MS ITEf ts PER CENT ITEMS ITEMS ITEMS ITEMS PER CENT UNIT APPLICABLE COMPLETED COMPLETED RTMAINING COVE R E D REQUIRED COMPLETED COMPLETED ST LUCIE 1 24 23 (95 ) 1 12 12 11 (91 1 ST LUCIE 2 25 24 195 l 1 12 12 11 (91 ) SUMMER 1 26 23 (88 ) 3 12 12 11 (91 ) SURRY I 26 25 (96 ) 1 12 12 11 (91 ) SURRY 2 26 25 (96 ) 1 12 12 11 (91 ) SUSOUEHANNA 1 20 20 (100) 0 11 10 10 (100) SUSQUEHANNA 2 20 20 (1001 0 11 10 10 (100) THREE MILE ISLAND 1 25 25 (100) 0 12 12 11 (91 ) TURMEY POINT 3 25 25 (100) 0 12 12 11 (91 ) TUR M E Y POINT 4 25 25 (1001 0 12 12 11 (91 ) VERMONT YANKEE 1 21 21 1100) 0 11 11 10 ?90 ) VDGTLE 1 27 27 (100) 0 12 12 11 (V! l O V0GTLE 2 27 27 (100) 0 12 12 11 (91 ) f WASHINGTON NUCLEAR 2 21 21 (100) 0 11 11 11 (100l WATERFORD 3 23 23 (100) 0 12 4 3 (75 I WOLF CREEK 1 27 26 (96 ) 1 12 12 11 (91 I ZION 1 26 26 (100) 0 12 12 11 (91 ) ZION 2 26 26 (100) 0 12 12 11 (91 ) TOTALS / AVERAGES 2579 2516 98 63 1248 1147 1055 92 4 l 1 1 Table 4.5 m

l 4.4 Status bv lssue Table 4.6 summarizes the status of implementation and verification of each GSI and sub issue. For each issue, the table shows the number of applicable plants, i the number and percentage of plants that have completed implementation, and the number of plants remaining to complete implementation. For those issues requiring verification of corrective actions, the table shows the number of plants covered by a TI, the number of plante requiring verification, and the number and percentage of plants that have completed verification. Of the 34 GSis and sub-issues,26 have been fully implemented. Two issues remain to be implemented at only one plant each and 2 more issues remain to be implemented at 2 or 5 plants each. The 5 issues discussed in Section 4.1 of this report account for 59 (94 percent) of the 63 items remaining to be implemented. I 1 SAFETY IS>UE MANAGEMEN T SYSTEM STATUS OF GSI PLANTS - SUPNARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED CCVERED REQUIRED COMPLETED. COMPLETED 40 31 31 (2001 0 NO SAFETY CONCERNS ASSOCIATED WITH PIPE BREAMS IN BWR SCRAM SYSTEM 41 35 35 (1001 0 YES 35 35 35 (100) BWR SCRAM DISCHARGE VOLUME SYSTEMS i 6733 107 90 (84 1 17 YES 107 106 94 (88 ) IMPROVED ACCIDENT MONITORING 70 66 52 (78 ) 14 NO PORV AND BLOCM VALVE RELIABILITY 75 (8076) 107 107 (100) 0 NO 8' ITEM 1.1 - POST TRIP REVIEW: PROGRAM DESCRIPTION & PROCEDURES 75 fB077) 107 107 (100) 0 YES 107 94 94 (100) ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTERFACE - RTS COMPONENT 75 (8078) 107 107 (1001 0 YES 107 95 95 (100) ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDURES & VENDOR RECOPH 75 18079) 107 107 (100) 0 YES 107 95 95 s100) ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO TECH SPECS - RTS CO 75 (8080) 72 72 (2001 0 YES 72 72 71 (98 ) ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDOR RELATED MODS 75 (8081) 72 72 (1001 0 YES 72 66 66 (100) I ITEMS 4.2 1 & 4.2.2 -PREVENTATIVE MAINT PROG FDR REACTOR TRIP BREAKERS 75 fB082) 57 57 (100) 0 NO ITEM 4.3 - AUTOMATIC ACTUATION DF SHUNT TRIP ATTACH FOR WEST & B&W r 75 (8085) 107 107 (1001 0 NO SALEM ATWS 1.2 DATA CAPABILITY 75 18086) 107 107 (100) 0 YES 107 95 95 (100) i SALEM ATWS 2.2 S-R COMPONENTS 75 (8087) 107 107 (1001 0 YES 107 95 95 (100) SALEM ATWS 3.2.1 & 3.2.2 S-R COMPONENTS 75 (8088) 107 107 (1001 0 YES 107 95 95 (100) I SALEM ATWS 3.2.3 T.S. S-R COMPOWENTS + 1 Table 4.6 i -n a.ay-,-,m.;, .-.,wn-r.n.- --,n,-----. v.-,. ,,w ,,..~w.en,-- .v-, ,e-

SAFETY ISSUE MANAGEMENT SYSTEM STATUS OF GSI PLANTS. Sup044RY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED 75 18090) 57 57 (100) 0 NO SALEM ATWS 4.3 W AND 88M T.S. 75 (8091) 7 7 (2003 0 Ng SALEM ATwS 4.4 B&W TEST PROCEDURES 75 (8092) 107 107 11001 0 YES 107 95 95 (100) SALEM ATWS 4.5.1 DIVERSE TRIP FEATURES 75 (8093) 107 107 (100) 0 NO SALEM ATwS 4.5.2 & 4.5.3 TEST ALTERNATIVES 86 34 34 (1001 0 YES 34 34 34 (100) LONG RANGE PLAN DEALING WITN STRESS CORROSION CRACKING IN BWR PIPING ,m 94 85 55 (84 1 10 NO ADDITIONAL LOW-TEMP OVERPRESSURE PROTECTION FOR LWRS 124 6 5 (100) 0 NO AUXILIARY FEEDWATER SYSTEM RELIABILITY A.16 2 2 (100) 0 NO STEAM EFFECTS ON 8WR CORE SPRAY DISTRIBUTION 8 10 4 4 (1001 0 NO BEMAVIOR OF BWR MARK III CONTAIISENTS 8-36 26 26 (1001 0 NO DEV OESIGN TEST & MAINT CRITERIA FOR ATM CLEANUP SYS AIR FILTER & ADSO 105 104 f99 ) 1 NO GL-80-014 LWR PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES GL 80-099 98 98 (2001 0 NO TECHNICAL SPECIFICATION REVISION FOR $NUBOER SURVEILLANCE GL-84-13 93 93 (100) e NO TECHNICAL SPECIFICATION FOR SNU68ERS GL-88-14 107 102 (95 ) 5 NO INSTRUMENT AIR SUPPLY SYSTEM PROBLEMS AFFECTING SAFETY-R" LATED EQUIP 4 GL-88-03 72 72 (100) 0 NO RESOLUTION OF GENERIC SAFETY ISSUE 93

STEAM BIIGING OF AUXILIARY FEE Table 4.6

I I SAFETY ISSUE MANAGEMENT SYSTEM r STATUS OF GSI PLANTS - Supe 4ARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REDVIRED COVERED REQUIRED COMPLETED COMPLETED GL-88-17 72 70 197 1 2 YES T2 T2 T1 (98 ) LOSS OF DECAY HEAT REMOVAL GL-89-13 107 94 (87 1 13 YES 107 98 20 (20 ) { SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EQUIPMENT GL-90-03 107 107 {1001 0 NO RELAXATION OF STAFF POS IN GEN LETTER 83-28, ITEM 2.2 PART 2 MPA-B023 107 106 (99 ) 1 NO DEGRADED GRID VOLTAGE o> co e l v I Table 4.6 l\\ - - - - - - ~ ~ - - -~

1 4.5 Conclusions After detailed review of the implementation and verification status of the resolution of GSis and sub-issues, the NRC staff has concluded the following:

The NRC closure process for GSis is adeouate to protect the public health and safety.

Licensees are making significant pro ress toward implementing GSI-related e s actions requested by the staff, and the framework exists to oversee future implementation of delayed items. Significant progress has been made in verifying the completion of e implementation actions associated with those GSis that have been resolved. The overall status of the 5 largely unimplemented GSis is generally acceptable e because of the relatively recent issuance of staff positions on three of the GSis, and projected implementation schedules for the remaining 2. -- 1

5 OTHER MULTIPLANT ACTIONS This section presents the overall status of implementation and verification of other MPAs not related to TMI Action Plan requirements, USIs, or GSis. The MPAs are applicable to the 107 licensed plants. Because each MPA may be tracked under different designations, Table 5.1 cross-references the MPA number and the SIMS number used in the tables and appendices of this report. { The agency has put-in-place several initiatives with the intention of reducing the number of administrative non-safety relevant requirements contained in licensing documents such as technical specifications. Because of the non-safety relevance of these items, the application for removal of these MPAs from the license has been left to the option of the licensee. For purposes of completeness, these MPAs were reported last year in Supplement 3 of NUREG-1435. However, because of the lack of safety relevance, the MPAs listed below are not being reported in this supplement. Sims item MPA Illig GL-88-16 D021 Removal of Cycle-specific Parameter Limits GL-88-12 D022 Removal of Fire Protection Tech Specs GL-88-06 D023 Removal of Organization Charts GL-87-09 D024 Mode Changes and LCO's - Tech Specs 3.0 and 4.0 GL-89-01 D025 Relocate RETS to Admin. Section of Tech Specs G L-89-14 D026 Elimination of 3.25 Requirement in Tech Spec 4.0.2 GL-90-02 D027 Alternative Reqmts for Fuel Assemblies in Tech Spec GL-90-09 D028 Visualinspection Frequency for Snubbers GL-91 -01 D029 Removal of W/D Schedule for RV Material Specimens GL-91 -08 D030 Remcval of Component Lists from Tech Specs GL-91-04 D031 TS Surveillance Interval Requirements for 24 Mo. Cycle GL-91 -09 D032 Mod of Surv int. for Elec Proto Assem in Power Supp GL-93-05 D033 Line item Tech Spec Improvement to Reduce Surv. Reg. GL-93-07 D034 Mod of Tech Spec Admin (Emergency and Security Leaks) GL-93-08 D035 Relocation of Tech Spec Tables RE: Instrument Resp. Time GL-94-01 D036 Removal of Accel Testing / Reporting Reg. for Emergency DG 5.1 Imolernantation Status Licensees achieve implementation of MPA items either by incorporating corrections } into the plant design before licensing or by making the modifications necessary to meet the requested, required or voluntary actions at licensed plants. The information presented here includes all MPA items related to the 107 licensed plants considered in this report. 1 l

SIMS Item Numbers and Corresponding MPA Numbers SIMS MPA flom No. SIM S Tide BL-88-08 X808 Thermal Stress in Piping BL-88-11 X811 Thermal Stratification in PZR Surge Line (BL 88-11) BL-92-01 X201 Thermal Lagging 330 (BL 92-01) BL-93-02 X302 Debns Pluggog of Emergency Core Cooling Suction Strainers BL-93-03 X303 Reactor Vessel Water level Instrumentat m in BWRs GL-8449 A019 Recorrinner Capability BWR Mark i GL-87-09 D024 Mode Changes & LCO's - Tech Specs 3.0.4 and 4.0.4 (GL 87-09) GL-88-01 B097 IGSCC Problemsin BWR Piping GL-88-11 A023 R.G.1.99 Rev 2 (pressurized Thermal Shock Rule) (GL 88-11) GL-88-20 B111 Indrvidual Plant Evaluations (GL 88-20) GL-89-01 D025 Relocate RETS to Admm Section of Tech Specs GL-89-04 A025 IST Reviews and Schedules (GL 89-04) GL-89-06 F072 Safety Parameter Display System - Response to GL 89-06 4 GL-89-10 B110 Motor Operated Valve Testing and SurveiAance (GL 89-10) 9 GL-89-16 B112 Installation of Hardened Wetwell Vent (GL 89-16) GL-91-08 D030 Removal of Component Lists from Tech Specs (GL 91-08) GL-91-11 L111 Vital Instruments Buses and Tie Breakers (GI-48,49) GL-92-01 B120 Reactor VesselStructuralIntegnty GL-92-04 B121 BWR Water LevelInstrumentation GL-92-08 L208 ThemW 330-1 Fire Bamers GL-93-04 L304 Rod Control System Failure and Withdrawalof Rod Control Cluster Assemblies MPA-B116 B116 Consader Results of Sponsored Motor-operated Tests (GL 89-10. Supp 3) MPA-B117 B117 Failure of Westinghouse SG Tube Mechanical Plugs (BL 90-01, Supp 2) MPA-8118 B118 IPE Extemal Events (GL 88-20. Supp 4) MPA-B122 8122 Loss of fib-Oilin Transmdters Manufactured by Rosemount (BL 90-01) MPA-B123 B123 Inaccuracy of MOV Diag. Equpment (BL 89-10, Supp 5) MPA-B124 B124 Debns Pluggog of ECC Suction Strainers (BL 93-02, Supp 1) MPA-B125 8125 Core Shroud Graclung Table 5.1

1 1 Approximately 89 percent of the MPA items have been implemented at licensed plants. Of the 6,951 applicable items, 6,307 have been completed and 644 remain open from an implementation standpoint. On average, each plant has approximately 6 remaining items to implement. No plant has more than 11 remaining items. Figure 5.1 presents the overall status of, and progress on, MPAs. Of the 107 licensed plants, none have fully implemented all applicable MPAs. Table 5.2 lists the number of unimplemented MPA items by plant. Appendix D lists the unimplemented MPA items by issue and projected implementation dates. MPAs are of a dynamic nature. New MPAs can and will be added as the situation dictates durin0 coming years. There are 16 MPAs with more than three unimplemented items. Figure 5.2 summarizes the implementation status of these issw. A brief description of these MPAs follows:

BL-92-01/GL-92-08 Thermo-Lao 330 Fire Barrier Svstem (X201/L20&1 To help ensure that each licensco defines and implements acceptable solutions to the Thermo Lag fire barrier issues, in December 1993, the staff sent a request for additional information (RAI) in accordance with 10 CFR 50.54(f) to each licensee relying on the Nuclear Energy Institute (NEl, formerly NUMARC) program. Licensees' responses were received and evaluated February through April of 1994. In May 1994, the staff sent the Commission the results of the review in SECY-94-128. The number of operating units that have yet to resolve the Thermo-Lag issues has been reduced from 83 to 59. In addition, the staff presented a list of proposed options to resolve the Thermo-Lag issue, recommended a course of action, and asked the Commission for guidance durin0 a briefing held on May 20,1994. The Commission approved the option which specified compliance with existing NRC requirements and permits plant-specific exemptions where justified.

NEl issued an application guide on July 7,1994, which provided the results of industry testing. In September,1994, the NRC staff issued follow-up letters to the Thermo Lag 50.54(f) letters sent to licensees in December 1993. The purpose of the follow-up letter is 1) to state the NRC's course of action to resolve the Thermo-Lag issue,2) to provide exemption guidance, and 3) to request completion of licensees' responses to the original RAI (50.54(f)) for licensees that deferred answering until the completion of industry testing and the issuance of the NEW application guide.

BL-93-02/MPA-B124 Debris Pluaaino of Emeraency Core Coolina Suction Strainers (X302/B124)

On May 11,1993, the NRC issued NRC Bulletin 93-02, " Debris Plugging of Emergency Core Cooling Suction Strainers." The bulletin discussed several instances of ECC suction blockage due to filtering action of fibrous material, and required certain compensatory actions by the licensees. Subsequently, a detailed study of a representative BWR 4 with a Mark I containment was l 73-

Summary of Unimnismented MPA items by Plant items Items items PLANT Remaining PLANT Remaining PLANT Remaining Arkansas 1 6 Grand Gulf 1 7 Point Beach 1 4 Arkansas 2 6 Haddam Neck 4 Point Beach 2 4 Beaver Valley 1 6 Harris 1 5 Prairie Island 1 6 Beever Valley 2 7 Hatch 1 11 Prairie Island 2 6 Big Rock Point 1 3 Hatch 2 9 Quad Cities 1 8 Braidwood 1 9 Hope Creek 1 5 Ouad Cities 2 9 Braidwood 2 9 Indian Pt 2 7 River Eend 1 6 Browns Ferry 2 7 Indian Pt 3 4-Robinson 2 3 Brunswick 1 5 Kewounee 4 Salem 1 6 Brunswick 2 5 LaSalls 1 8 Salem 2 6 Byron 1 7 LaSalle 2 8 San Onofre 2 6 Byron 2 7 Limerich 1 6 San Onofre 3 6 Callaway 1 5 Limericle, 2 6 Seabrook 1 3 Calvert Cliffs 1 4 Maine bnkee 4 Sequoyah 1 5 Calvert Cliffs 2 4 McGuire 1 5 Sequoyah 2 6 Catawba 1 5 McGuire 2 5 South Texas 1 6 Catawba 2 5 Millstone 1 5 South Texas 2 6 4 Clinton 1 6 Millstone 2 7 St. Lucie 1 5 A Comanche Peak 1 5 Milistone 3 7 St. Lucia 2 5 Comanche Peak 2 2 Monticello 5 Summer 1 7 Cook 1 5 Nine Mile Pt 1 9 Surry 1 6 Cook 2 4 Nine Mile Pt 2 6 Surry 2 7 Cooper Station 10 North Anna 1 8 Susquehanna 1 9 Crystal River 3 5 North Anna 2 8 Susquehanna 2 9 Davis-Besse 1 9 Oconee 1 4 Three Mile Island 1 4 Diablo Canyon 1 6 Oconee 2 4 Turkey Pt 3 5 Diablo Canyon 2 6 Oconee 3 4 Turkey Pt 4 5 Dresden 2 10 Oyster Creek 1 7 Vermont Yankee 1 6 Dresden 3 9 Palisades 6 Vogtle 1 7 Duane Arnold 7 Palo Verde 1 4 Vogtle 2 7 Farley 1 6 Palo Verde 2 5 Washington Nuclear 2 5 Farley 2 6 Palo Verde 3 6 Waterford 3 4 Fermi 2 11 Peach Bottom 2 6 Wolf Creek 1 6 Fitzpatrick 4 Peach Bottom 3 7 Zion 1 5 Ft Calhoun 1 3 Perry 1 5 Zion 2 5 Ginna 10 Pilgrim 1 6 9 Table 5.2

Other MPA Items implementation Status at Licensed Plants l 8000 7000 - 6000 - i 5000 - 4000 - 3000 - 0 i i Applicable implemented Unimplemented Figure 5.1 'I A

i. Summary of Sixteen Unimplemented MPAs l 120 -107 107 106 107 107 107 98 {l, 92 100 -- l ,7 81 L 80 - i g 80 -- 4o -- 34 30 19 20 i 15 20 -- 9 4 4 0-- -k I i I BL-92-01 BL-93-02 BL-93-03 GL-8445 GL-88-20 GL-89-10 GL-92-01 GL-97 J8 (X201) (X302) (B121) (A019) (B111) (8110) (B120) (L'A8) SIMS Item Number i O Applicable Plants O implemented Plants O unimpsemented Plants Figure 5.2 l \\ i

120 -- 107 105 106 103 100 -- 87 l M-- I f 67 E 60 -- 49 49 35 40 _ 31 33 33 35 34 31 d 0 i i i i i i i GL-92-04 GL-93-04 GL-94-03 MPA-B116 MPA-B118 MPA-B122 MPA-B123 MPA-B124 (X303) (L304) (B125) (B116) (B118) (B122) (B123) (B124) SIMS Item Number C Applicable Plants O Implemented Plants O Unimpismented Plants Figure 5.2 continued

contracted by the staff. The preliminary results of this study showed that insulation debris generated during a LOCA could potentially be transported to l the ECCS suction strainers and clog them. This preliminary finding combined with Perry and Barseback events led the staff to issue NRC Bulletin 93-02, Supplement 1. The NRC issued the bulletin supplement on February 18,1994. The proposes of the bulletin supplement were: (1) to inform BWR licensees and PWR licensees about the vulnerability of ECCS suction strainers in BWRs and containment sumps in PWRs to clogging during the recirculation phase of a loss-of-coolant accident (LOCA). (2) to request that BWR licensees take the appropriate actions to ensure reliability of the ECCS in view of the information discussed in this bulletin supplement regarding the vulnerability of the ECCS strainers to clogging. (3) to require that BWR licensees report to the NRC whether and to what extent the requested actions will be taken and to notify the NRC when actions associated with this bulletin supplement are complete. All BWR licensees have responded to the supplement and staff review is underway. 1 e BL-93-03/GL-92-04 Reactor Vessel Water Level Instrumentation in BWRs (B121/X303) The staff issued GL 32-04, " Resolution on the issues Related to Reactor Vessei Water LevelInstrumentation in BWRs Pursuant to 10 CFR 50.54(f)" on August 19,1992, to alert licensees of BWRs to errors related to instrumentation accuracy in water level instrumentation and to the results of the staff's review of the BWROG's generic analysis of these errors. The staff also requested addressees to (1) determine the impact of these errors on automatic safety system response, operator short-and long-term actions, and emergency operating procedures at their facilities; (2) take short-and long-term corrective actions; and (3) submit a report that includes ths results of their i determinations, a discussion of their short-and long-term actions, and the schedule for completion of their long-term programs. All addressees responded by September 28,1992. Most licensees requested deferral of the long-term corrective actions to allow BWROG to complete testing and analysis of the BWR water levelinstrumentation. The staff accepted delays in the implementation of long-term corrective actions pending BWROG development of plant and/or procedure modifications by July 1993. Following an event at the WNP-2 plant in January 1993, additional analyses by the BWROG reveeled additional safety concerns related to RPV water level.

l instrumentation at low pressures following normal depressurizations. This led the staff to issue NRC Bulletin 93-03 on May 28,1993, requesting additional actions by the addressees. These actions were to (1) provide additional procedures and training to address the new concerns and (2) implement, at the first cold shutdown after July 30,1993, hardware modifications to ensure high functional reliability of the RPV water level instrumentation for long-term operation. Addressees have provided their responses. All BWR licensees have completed the short-term compensatory actions requested in BL-93 03. At this time, licensees for 35 of the 36 affected plants have either completed installation of hardware modifications or are currently shutdown and will install the hardware modifications prior to restart. The remaining licensee has committed to complete modifications during the next cold shutdown, and is currently scheduled to shutdown for refueling in January l 1995. Based upon the licensees' safety analyses and the short-term compensatory measures provided in response to GL 92-04 and BL-93-03 that have been taken, the NRC staff considers these schedules to be acceptable. i e GL-84-09 Recombiner Caoability Reauirements of 10 CFR 50.44 (c)(3)(ii) (A019) As a result of the TMI-2 accident, it became clear that the amount of hydrogen produced from the metal-water reaction was far in excess of that previously considered by the NRC staff during the licensing process. As a result, the staff revised 10 CFR 50.44, " Standards for Combustible Gas Control Systems," effective January 4,1982 (46 FR 58484) to address this safety concern. For plants with Mark I and Mark ll type containments, the staff determined that containment inerting (with nitrogen) and recombiner capability were sufficient measures to accommodate hydrogen from a 75-percent metal-water reaction without resulting in a burnable mixture. Certain licensees with Mark I containment took exception to the staff's position of providing recombiner capability because they believed the assumptions in NEDO-22155 were questionable. Therefore, using the models in NEDO-22155, they calculated that a typical Mark I design equipped with containment inerting was sufficient to preclude a burnable mixture resulting from a 75 percent metal-water reaction for the 30 days following an accident, both within the design-basis-accident (DBA) envelop and slightly beyond. The NRC staff concluded that, on balance, costs outweighed the benefits to address this limited situation. To reflect this position, the NRC issued GL 84-09, dated May 8,1984. GL 84-09 allowed licensees with Mark i type containments that rely on i purge /repressurization systems as a mearn of hydrogen control, an option in lieu of insta!'ing recombiner capability if they met the following conditions: (1) the plant has technical specifications (limiting conditions for operation) requiring that the containment is less than 4-percent oxygen while inerted, (2) the plant has only nitrogen or recycled containment atmosphere for use in all pneumatic control systems within containment, and (3) there are no significant sources of Oxygen in containment other than that resulting from radiolysis of the reactor coolant. j

GL-88-20 Individual Plant Examination for Severe Accident Vuharability j

10 CFR 50.54(f) (B111) The NRC issued GL 88-20, " Individual Plant Examination for Severe Accident Vulnerability," on November 23,1988, to request addressees to perform an individual plant examination (IPE) of their plant specific internal event severe accidents and report the results of their analysis. The NRC issued Supplement 1 to GL 88-20, " Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR 50.54," on August 29,1989, requiring licensees to submit an IPE to identify plant-specific severe accident vulnerabilities using probabilistic risk analysis methodology. The IPE effort is more complex than estimated. Severallicensees have delayed submittal of IPEs from 2 to 18 months. The staff has issued 18 evaluation reports documenting the results of the IPE review. As of June 30,1994, all i IPEs had been submitted. The staff expects to complete all reviews by mid-1 1996. l e GL-89-10/MPA-B123 Safety Related Motor-Ooerated Valve Testina and l Surveillance (B110/B123) NRC staff issued GL 89-10 to inform licensees of problems concerning the operability of safety-relater lotor-operated valves, and request addressees to (1) establish programs to demonstrate the operability of these valves and to ensure continued operability over the life of the plant, (2) provide a commitment to establish such a program and complete the demonstration of operability-l within the timeframe specified in GL 89-10, and (3) report completion of the demonstration phase of their programs. The subject matter of this generic letter is related to that of BL 85-03, " Motor-Operated Valve Common Mode l Failures During Plant Transient Due to improper Switch Setting," and its l supplements. Supplements 1 through 4 of GL 89-10 were addressed in Supplement 2 of NUREG-1435. I Supplement 5, " Inaccuracy of Motor-Operated Valve Diagnostic Equipment," j was issued on June 28,1993, to request licensees to reexamine their MOV programs in light of new information on MOV diagnostic equipment inaccuracies and to identify measures taken or planned to account for uncertainties in valve thrust. Licensees were also to determine the schedule necessary to satisfy this supplement. All power reactor licensees have submitted responses to this ! r

supplement. Licensees indicated that many MOVs had the potential for underthrusting or overthrusting as a result of the higher than expected inaccuracy of MOV diagnostic equipment. Consequently, some licensees reported that MOVs have been retested, adjusted, or modified to resolve the concerns regarding the accuracy of MOV diagnostic equipment. Licensees have j incorporated the margins necessary to account for diagnostic equipment inaccuracies in their MOV testing program and accounted for schedule adjustment. i Supplement 6, "Information on Schedule and Grouping, and Staff Responses to Additional Public Questions," was issued on March 8,1994. This supplement includes discussions of schedule extensions, grouping of MOVs, and use of probabilistic risk assessment in the implementation of GL 89-10. Licensee responses are voluntary, and the staff is currently evaluating several submittals regarding schedule extensions.

GL-92-01 Reactor Vessel Structural Inteority (B1201 l

NRC issued GL 92-01, " Reactor Vessel Structural integrity," on February 28, 1992. Revision 1 was issued o:. March 6,1992. The background section i concerning NRC's assessment of embrittlement in the Yankee Rowe reactor vessel was updated by Revision 1 to better reflect the licensee's extensive technical efforts regarding reactor vesselintegrity. Responses were requested to be submitted within 120 days from issuance of GL 92-01, Revision 1. All licensees have responded. GL 92-01 is part of the staff's continuing program to evaluate reactor vessel i integrity. The information provided in response to GL 92-01 is being used to confirm that all licensees are complying with the requirements of 10 CFR 50.60 and 10 CFR 50.61, Appendices G and H to 10 CFR Part 50, and are fulfilling i the requirements of GL 88-11, "NRC Position On Radiation Embrittlement of Reactor Vessel Materials and Its impact On Plant Operations." Closeout letters have been sent to all licensees indicating that the NRC staff has completed its review of their responses to GL 92-01 and has determined that the information requested in GL 92-01 has been provided by all of the licensees. It was further noted in the letters, that the data provided by each licensee has been entered in a computerized data base which has been designated the Reactor Vessel Integrity Data Base (RVID) and requested that each licensee verify that the data for its plant was accurately entered in the RVID. The RVID is being updated to correct any inaccuracies identified. The NRC staff is in the process of completing a NUREG report which will document the results of its reassessment of reactor pressure vesselintegrity for all of the domestic commercial nuclear power plants. This status report is expected to be issued in October or November of 1994. In addition, the RVID 1...

will be updated periodically based on the NRC staff's assessments of the latest reactor vessel information provided by the industry and licensees. The results of the NRC staff's assessments will be included in yearly updates of the NUREG. e GL-93-04 Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies.10 CFR 50.54(f) (L304) The NRC issued GL 93-04 on June 21, 1993,(1) to notify addressees about a single failure vulnerability within the Westinghouse solid-state rod control system that could cause an inadvertent withdrawal of control reds in a sequence resulting in a power distribution not considered in the design basis analyses and (2) to require that all action addressees provide the NRC with information describing their plant-specific findings related to this issue and actions taken. The GL was addressed to all holders of operating licenses or constru : tion permits for Westinghouse-designed nuclear power reactors except Haddam Neck. The GL requested licensees to assess within 45 days if their licensing basis is still satisfied with regard to single failure in the rod control system in light of the Salem event. If the licensing basis is not satisfied, the NRC requested licensees to provide an assessment of the impact and describe any compensatory short-te... actions taken within 45 days and provide a plan and schedule for long-term resolubn ithin 90 days. On July 26,1993, the NRC granted relief to the schedules a exte.d the licensing basis assessment portion of the 45-day response to the 90-day response, in response to a request from the Westinghouse Owners Group (WOG). All licensees have provided their 45-day and 90-day responses. The responses generally indicated that they were following the WOG's efforts and would update their responses upon completion of the WOG's efforts. For the interim, the responses generally indicated that additional instructior and training to heighten operator awareness of a potential rod control sys6m failure was provided, and that a three-dimensional safety analysis shows that there is no safety significance for affected Westinghouse plants for Salem-type rod withdrawal. The long-term WOG efforts include a current timing order change to the rod control system and a new surveillance test. The timing change does not affect normal rod motion, but prevents asymmetric rod withdrawal should Salem-type failure occur. The modification was successfully tested at the Ginna Station on April 15,1994. Following the successful testing of Ginna Station, the WOG submitted the following pertinent information to the NRC in July 1994: (1) WCAP-13864, Rev.1, " Rod Control System Evaluation Program," (2) WOG Technical Bulletin -8 2- )

NSD-TB-94-05-RO, " Rod Control CRDM Timing Change," (3) "WOG Recommended Rod Control Surveillance Test," (4) Response to NRC Questions on A-Factor Methodology Validation in WCAP-13803, Rev.1, (Proprietary), " Generic Assessment of Asymmetric Rod Control Cluster Assembly Withdrawal," and (5) " Rod Control System Logic Cabinet /CRDN Timing Change," (includes the WOG's 10 CFR 50.59 evaluation of the new current timing order). The NRC staff is currently reviewing these documents and expects to complete their evaluation by October 1994. e GL-94 03 Interoranular Stress Corrosion Crackina of Core Shrouds in Egilina Water Reactors (8125) The NRC issued GL 94-03, "Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors," on July 25,1994. The purpose of this GL is to request each boiling-water reactor (BWR) with core shroud to: (1) inspect the core shroud no later than the next scheduled refueling outage, and perform an appropriate evaluation and/or repair based on the results of the inspection; and (2) perform a safety analysis supporting continued operation of the facility until inspections are conducted. Each of the BWRs is required to respond with their schedule for inspection of the core shroud and a safety analysis supporting continued operation of the facility within 30 days from the date of the GL. In addition, no later than 3 months prior to performing the core shroud inspections, each licensee must submit an inspection plan and plans for evaluation and/or repair of the core shroud based on the inspection results. o MPA-B116 Retults of NRC Testino of MOVs (GL-89-10 Suco 3) (B116) On June 5,1990, the staff issued IN 90-40, "Results of NRC-Sponsored Testing of Motor-Operated Valves (MOVs)." The tests revealed that the valves required more thrust for opening and closing under various differential pressure and flow conditions than would have been predicted from standard industry calculations using typical friction factors. Therefore, the staff issued Supplement 3 to GL 89-10 on October 25,1990, wiiich described required actions for licensees of BWRs. Licensees were required to provide (1) criteria reflecting operating experience and the latest test data that were applied in determining whether the deficiencies exist in the subject MOVs, (2) a list of the MOVs found to have deficiencies, and (3) a schedule for the necessary corrective action. e MPA-B118 IPE External Events (GL-88-20 Suco 4) (B118) The staff issued Supplement 4 to GL 88-20 on June 28,1991, to initiate the IPE process for external events. Five categories of external events were specified, and licensees were required to submit to a schedule and methodology -8 3-mm-----

ll by December 26,1991. Licensees were requested to submit the results of the individual plant examination of external events (IPEEE) within 3 years of the issuance date of Supplement 4, or no later than June 28,1994. A copy of NUREG-1407, " Procedural and Submittal Guidance for the IPEEE for Severe Accident Vulnerabilities," was sent to each licensee with Supplement 4. All licensee schedules for submittal of their IPEEEs have been received and reviewed jointly by NRR and RES. A common difficulty with a large number of the responses was the linkage of IPEEE to implementation of the USl A-46 l resolution required by GL 87-02 to verify seismic adequacy of mechanical and electrical equipment. Supplement 4 to GL 88-20 encouraged licensees to combine the walkdown that would be required for the seismic portion of the IPEEE with the walkdown required by GL 87-02. Supplement 1 to GL 87-02 was issued on May 22,1992, approving the seismic qualification utility group generic implementational procedure for USl A-46 implementation and starting the clock for both A-46 and the IPEEE. Licensees were advised that the latest acceptable date for IPEEE submittal would be June 1995. A second round of licensee responses indicated that the best effort by the industry will have the IPEEEs for 72 plants submitted by the l target date of June 1995 but for the remaining 37 plants, the submittal dates l will range from September 1995 to July 1997. As of August 1,1994, ten l reports have been submitted. l There are a small number of plants that have unique problems requiring a more customized response (1) because the licensee proposed alternative methods or failed to provide any method at all for its IPEEE or (2) because the licensee's i plant was one of the eight singled out by the Eastern United States Seismic Hazards Program as needing further NRC staff evaluation, j e MPA-B122 Loss of Fill-Oilin Transmitters Manufactured by Rosemount f (BL-90-01) (B122) r On April 21,1989, the staff issued Information Notice 89-42, "lFailure of Rosemount Models 1153 and 1154 Transmitters," to alert the tndustry of the loss of oil-fill problem. On March 9,1990, the staff issued Bulletin 90-01, " Loss of Fill-Oilin Transmitters Manufactured by Rosemount," to request the l licensees to promptly identify and to take appropriate corrective action for Model 1153, Series B, Model 1153, Series D, and Model 1154 transmitters that may have the potential for leaking fill-oil. From mid 1990 through 1992, the j staff reviewesd information from the (1) licensee responses to Bulletin 90-01, (2) data from related licensee event reports, (3) visits to the sites, (4) NUMARC Report 91-02, " Summary Report of NUMARC Activities to Address Oil Loss in Rosemount Transmitters," and (5) meetings with the industry. The staff found [ a relationship between operating pressure and time-in-service that can be j l

trended for use in identifying transmitters that are most likely to fail. The staff has concluded that (1) the requested actions in Bulletin 90-01 were insufficient in that they did not provide the desired high functional reliability and (2) a supplemental bulletin would be needed for ensuring appropriate licensee corrective action to the loss of fill-oil problem. Subsequently, on December 22,1992, the staff issued Bulletin 90-01, Supplement 1, " Loss of Fill-Oilin Transmitters Manufactured by Rosemount," to request new action from the licensees. Specifically, licensees were to provide information on specified model: of the Rosemount transmitters manufactured before July 11,1989, that are in use or may be used in the future. The information should detail the use of the devices in either a safety-related system or a system governed by the NRC's ATWS (anticipated transient without scram) requirements where normal operating pressure is greater than 500 pounds per square inch. Requested corrective action includes the replacement of the suspect transmitter or the use of an enhanced surveillance monitoring program until the transmitter reaches the time-in-service pressure criterion recommended by the vendor. Responses to the supplemental bulletin have been received from all applicable licensees; and as of September 30,1994, responses for 65 reactor units have been reviewed and found to have completed the reporting requirements with the remaining responses to have a scheduled completion date of December 31, 1994. Additionally, the NRC staff has developed an action plan to address implementation of the recommendations resulting from the further assessment of Rosemount transmitter problems performed by the Rosemount Transmitter Review Group (RTRG) as documented in its October 12,1993 report. These actions are as follows:

1. On March 17,1994, the NRC staff issued a temporary instruction (Tl 2515/122) for conducting inspection of the augmented surveillance programs for Rosemount transmitters at operating nuclear power plants. As of October 1994, inspections were completed at five plant sites.

2. On February 17,1994, the NRC staff held the first of several periodic meetings with Rosemount, Inc. to exchange information on Rosemount transmitter performance. A second meeting was held September 15,1994, at the Rosemount, Inc. facility in Eden Prairie, Minnesota. The next meeting is scheduled for Spring 1995 with the final meeting to follow approximately 6 months from then.

3. In January 1994, the NRC staff completed it first review of Nuclear Plant Reliability Data Systems (NPRDS) data on Rosemount transmitter failures.

This review indicated a significant decrease in the number of Rosemount -8 5-

transmitter failures since 1990. This finding, as well as the finding from the second data review completed in July 1994 was consistent with Rosemount, Inc. Information on transmitter performance. The third data collection and analysis effort is planned for January 1995, followed by a final analysis in 6 months.

4. The NRC staff will review EPRI Report TR-102908 dealing with Rosemount transmitter concerns.

5.2 Verification Status For generic items such as MPAs, NRR issues Tls for those items that need to be verified in the field by the NRC staff after licensees have implemented the corrective actions specified in the MPA resolution. The NRC performs these inspections, consistent with other inspection priorities, to verify proper implementation of the requirements. Verification is not considered complete until the required inspection is conducted in accordance with the Tl, and an inspection report has been issued documenting that requirements have been adequately satisfied by the licensee. On occasion, there may be issues for which the requirements specified in the Tl for safety verification inspection are completed before total implementation of all aspects of the issue's resolution by the licensee. Tis provide guidance for the field verification of licensee implementation of other MPAs. The NRC issued 17 Tis for 17 MPA issues which require verification. The 17 issues cover a total of 990 items at the 107 licensed plants. Upon initial inspection of certain items and further review by the regional offices,108 items covered by the Tis were found to be inapplicable from a verification standpoint, leaving a total of f'82 items requiring verification. The majority of items found not applicable are cas; > in which initial inspection did not reveal any significant findings and for wi.-- 5 further inspection effort cannot be justified. As of September 30,199.L 633 items (70 percent) had been verified. Tl designations and the corresponding MPAs are summarized in Table 5.3. Table 5.4 summarizes the items remaining to be verified. Temporary Instruction (TI) 2515/121, Installation of Hardened Wetwell Vent (GL-89-16), was issued May 24,1994 and Tl 2515/122, Loss of Fill-oilin Transmitters Manufactured by Rosemount (MPA-B122), was issued March 17,1994. ! j

Temporary Instructions for Resolved MPAs SIMS ltem M!% SIMS Title Tl Number BL-79-15 8031 Deep Draft Pump Deficiencies 2500/001 BL-80-11 B059 Masonry Wall Design 2515/037 BL-88-04 X804 Sl Pump Failure (Bulletin 88-04) (Old MPA B103) 2515/105 BL-88-07 X807 Power Oscillations in Boiling Water Reactors (BWRs) 2515/099 GL-80-02 A015 Quality Assurance Requirements Regarding Diesel 2515/093 Generator Fuel Oil GL-81-21 B066 Natural Circulation Cooldown 2515/086 GL-83-08 D021 Modification of Vacuum Breakers on 2515/096 Mark i Containments GL-89-04 A025 Guidance on Accepting inservice Testing Programs 2515/114 GL-89-07 L907 Power Reactor Safeguards Contingency Planning for 2515/102 Surface Vehicle Bombs GL-89-10 B110 Safety Related Motor Operated Valve Testing and 2515/109 Surveillance GL-89-16 B112 Installation of Hardened Wetwell Vent 2515/121 GL-92-04 X303 Reactor Vessel Water Level Instrumentation in BWRs 2515/119 MPA-8003 B003 PWR Moderator Dilution 2515/094 MPA-8011 B011 Flood of Equipment important to Safety 2515/088 MPA-8041 B041 Fire Protection - Final Technical Specification 2515/062 (including SER Supplements) MPA-B122 B122 Loss of Fill-oilin Transmitters Manufactured by 2515/122 Rosemount MPA-C002 C002 BWR Recirculation Pump Trip (ATWS) 2515/095 Table 5.3 I =

Summary of Other MPA Items Requiring Verification SIMS Item Plants Plants Plants E9.1tLtd Reautred Verified BL-88-04 St PUMP FAILURE 107 38 35 GL-81-21 NATURAL CfRCULATION COOLDOWN 72 67 61 GL-83-08 MOOlFICATION OF VACUUM BREAKERS ON 21 21 20 MARKICONTAINMENTS GL-89-04 GUIDANCE ON ACCEPTABLE INSERVICE 40 31 19 TESTING PROGRAMS i GL-89-10 SAFETY-RELATED MOTOR-OPERATED 107 107 26 VALVE TESTING AND SURVEILLANCE GL-89-16 INSTALLATION OF A HARDENED WETWELL 22 22 0 VENT h GL-92-04 REACTOR VESSEL WATER LEVEL 35 35 16 INSTRUMENTATION IN BWRs MPA-0011 FLOOO OF EQUIPMENTIMPORTANTTO 9 3 1 SAFETY MPA-8041 FIRE PROTECTION - FINALTECH SPECS 63 60 59 (INCLUDING SER SUPPLEMENTS) MPA-B122 LOSS OF FILL-OfL IN TP*NSMITTERS 107 107 5 MANUFACTURED BY ROSEMOUNT NOTE-Plants Covered are those for which MPAs are applicable Plants flequired are those plants requiring field venficatiort. Plants covered but for which field verification is not necessary have implemented the resoluton in a manner not requiring plant hardware changes-Table 5.4

5.3 Status bv Plant Table 5.5 summarizes information on the status of implementation and verification of MPAs at all licensed plants. For each plant, the table shows the total number of applicable items, the number and percentage of items implemented, and the number of items remaining to be implemented. For those MPAs that require the NRC to verify implementation actions, the table shows the :: umber of items covered by a Tl at each plant, the number of items requiring verification, and the number and percentage of items completed. Appendix D lists the unimplemented MPA items by plant and gives projected implementation dates. Of the 107 plants, none have completely implemented all MPA items. On average, each plant has approximately 6 remaining items to implement. No plant has more than 11 remaining items. SAFETY ISSUE MANAGEMENT SYSTEM STATUS OF OTHER MPA(S) - SUPNARY BY UNIT IMPLEMENTATION VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PER CENT i UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQt/ IRED COMPLETED COMPLETED ARMANSAS 1 97 91 (93 ) 6 11 9 7 (77 t [ ARKANSAS 2 82 76 (92 ) 6 to 8 6 (75 i BEAVER VALLEY I 89 83 (93 ) 6 10 9 8 (88 i BEAVER YALLEY 2 39 32 (82 ) 7 8 6 5 (83 ) BIG ROCh POINT 1 70 67 (95 ) 3 11 10 6 (59 i BRAIDWOOD I 39 30 (76 ) 9 7 6 4 (66 t BRAIDWOOD 2 37 28 (75 ) 9 6 5 3 159 BROWNS FERRY Z 76 69 (90 ) 7 12 12 9 1 75 i URUNSWICK 1 79 74 (93 ) 5 12 12 6 1 50 BRUNSWICK 2 78 73 (93 ) 5 12 11 7 1 63 BYRON 1 39 32 (82 ) 7 6 5 3 (59 I BYRON 2 37 30 (81 ) 7 6 5 3 (59 e CALLAWAY 1 39 34 (87 ) 5 6 5 3 (59 CALVERT CLIFFS 1 87 83 (95 ) 4 10 9 8 (88 O CALVERT CLIFFS 2 83 79 (95 ) 4 10 S' 8 (88 CATAWBA 1 38 33 (86 ) 5 6 5 2 i 39 CATAWBA 2 37 32 (86 ) 5 6 5 2 i 39 CLINTON 1 37 31 (83 3 6 8 7 4 1 57 COMANCHE PEAK 1 78 73 (93 ) 5 10 6 4 (66 i COMANCHE PEAK 2 75 73 (97 l 2 10 4 2 50 COOK 1 87 82 (94 i 5 9 8 6 1 75 COOK 2 86 82 (95 i 4 9 8 6 1 75 COOPER STATION 81 71 (87 ) 10 13 11 7 1 63 t CRYSTAL RIVER 3 87 82 (94 ) 5 11 11 8 1 72 l-DAVIS-BESSE 1 81 72 (88 ) 9 10 7 5 (71 i DIABLO CANYON 1 45 39 (86 ) 6 7 7 6 L85 i DIABLO CANYON 2 40 34 (84 ) 6 6 6 5 '83 DRESDEN 2 83 73 (87 1 10 14 14 9 64 1 DRESDEN 3 82 73 (89 I 9 13 13 8 61 1 DUANE ARNOLD 83 76 (91 1 7 14 13 8 i 61 1 FARLEY 1 85 79 (92 ) 6 9 9 7 1 77 l FARLEY 2 51 45 (88 I 6 8 8 6 (75 i FERMI 2 37 26 (70 t 11 3 8 4 50 1 FITZPATRICK 81 77 (95 1 4 14 12 10 83 i FORT CALHOUN 1 98 95 (96 1 3 11 9 7 77 GINNA 89 79 (88 1 10 11 10 8 i 79 i GRAND GULF 1 38 31 (81 1 7 8 7 5 71 HADDAM NECK 88 84 195 4 10 10 8 1 79 HARRIS 1 37 32 (86 1 5 6 5 2 (39 t HATCH 1 79 68 (86 ) 11 12 11 7 ' 63 HATCH 2 73 64 (87 l 9 13 12 8

66 l

MOPE CREEK 1 37 32 (86 1 5 8 7 5 . 71 INDIAN POINT 2 93 86 (92 1 7 11 9 7 (77 INDIAN POINT 3 86 82 (95 ) 4 10 9 7 (77 i Table 5.5 m.

5 A F_E T Y ISSUE MANAGEMENT SYSTEM STATUS OF OTHER MPAIS) - Supe #RY BY UNIT IMPLEMENTATION VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PER CENT UNIT APPLICA6LE COMPLETED COMPLETED REMAININO COVERED REQUIRED COMPLETED COMPLETED MEWAUNEE 94 90 (95 4 to 9 ~7 1 77 e LASALLE 1 38 30 (78 8 8 7 4 1 57 LASALLE 2 38 30 (78 8 8 7 4 i 57 i LIMERICK 1 37 31 (83 1 6 7 6 6 l 160 l t 6 7 6 6 100 1 LIMERICM 2 35 29 (82 l MAINE YANMEE 93 89 (95 ) 4 12 11 9 1 St MCGUIRE 1 46 41 (89 I 5 6 5 3 (59 i 5 6 5 3 (59 MCGUIRE 2 40 35 (87 5 13 11 9 (81 MILLSTONE 1 76 71 (93 1 7 10 9 7 177 MILLSTONE 2 89 82 (92 MILLSTONE 3 36 29 (80 1 7 6 6 4 1 66 MohTICELLO 81 76 (93 ) 5 13 12 7 1 58 NINE MILE POINT 1 84 75 (89 ) 9 13 13 10 (76 NINE MILE POINT 2 35 29 (82 ) 6 7 6 4 (66 I NORTH ANNA 1 68 60 (88 ) 8 10 10 8 (79 i Y NOR H ANNA 2 51 43 (84 I 8 8 7 5 (71 DC0 HEE 1 90 56 (95 4 11 10 8 (79 OCONEE 2 90 86 (95 4 11 10 8 (79 i OCONEE 3 89 85 (95 4 11 10 8 (79 i OYSTER CREEK 1 78 71 191 7 14 14 12 (85 I PALISADES 90 84 (93 6 12 9 6 (66 I PALO VERDE 1 35 31 (88 4 6 6 5 183 i PALO VERDE 2 32 27 (84 1 5 6 6 5 1 83 I PALO VERDE 3 34 28 (82 3 6 '6 6 5 1 83 i PEACH BOTTOM 2 80 74 (92 ) 6 13 12 11 (91 1 PEACH BOTTOM 3 79 72 (91 ) 7 13 12 11 (91 1 PERRY 1 36 31 186 1 5 8 7 4 (57 1 PILGRIM 1 84 78 i 92 1 6 13 12 10 183 POINT BEACH 1 91 87 i 95 4 11 10 7 1 69 POINT BEACH 2 91 87 ' 95 4 10 9 6 i 66 PRAIRIE ISLAND 1 90 84 1 93 6 9 3 6 ' 75 PRAIRIE ISLAND 2 90 84 1 93 1 6 9 8 6 (75 i QUAD CITIES 1 85 77 (90 1 8 13 12 7 (58 I OUAD CITIES 2 34 75 (89 l 9 13 12 7 158 I RIVER BEND 1 35 29 i82 6 7 6 3 1 50 i RD81NSON 2 87 84

96 3

10 9 7 1 77 I SALEM 1 89 83 1 93 6 10 10 8 1 79 I SALEM 2 54 48 ' 88 6 9 9 7 1 77 I SAN ONOFRE 2 37 31 1 83 6 6 6 5 - 83 SAN ONOFRE 3 37 31 1 53 i 6 6 6 5 (83 i 91 t 3 6 6 5 (83 SEABROOK 1 37 34 SEQUOYAH 1 45 40 1 88 ) 5 6 6 4 (66 SEQUOYAH 2 38 32 (84 6 6 6 4 (66 i SOUTH TEXAS 1 36 30 (83 6 6 4 2 (50 i Table 5.5

i SAFETY ISSUE MANAGEMENT $YSTEM STATUS OF OTHER MPA(S) - SUtmARY BY UNIT IMPLEMENTATION VERIFICATION ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PER CENT UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQUIRED COMPLETED COMPLE.TED SOUTH TEXA5 2 34 28 (82 6 8 4 2 (50 1 ST LUCIE 1 90 85 (94 i 5 11 11 8 (72 ST LUCIE 2 36 31 (86 5 6 8 4 1 es SUbe'ER 1 40 33 (82 ) 7 6 6 2 1 33 SURRY 1 94 88 (93 ) 6 11 10 7 i 69 SURRY 2 97 90 (92 ) 7 11 10 7 1 69 SUSCUEHANNA 1 37 28 (75 ) 9 8 6 4 88 i SUSCUEHANNA 2 37 28 (75 ) 9 8 8 4 SS THREE MILE ISLAND 1 95 91 (95 ) 4 10 9 8 88 l TURKEY POINT 3 SF 92 (94 ) 5 11 9 7 ' 77 TURMEY POINT 4 98 93 (94 l 5 11 9 7 i 77 VERMONT YANKEE 1 81 75 (92 ) 6 14 12 le l 83 ) V0GTLE 1 38 31 (81 f 7 6 6 3 (50 ) M V0GTLE 2 32 25 (78 i 7 6 6 3 (50 t 1 N WASHINGTON NUCLEAR 2 39 34 (87 t 5 7 7 6 (85 i WATERFORD 3 34 30 (88 l 4 6 4 2 (50 i WOLF CREEK 1 37 31 (83 ) 6 8 4 2 (50 i ZION 1 94 89 (94 5 9 7 5 (11 i ZION 2 94 89 (94 5 9 7 5 (71 1 TCTALS / AVERAGES 8951 6307 39 644 990 882 833 70 1 1 Tatde 5.5

l 5.4 Status by issue Table 5.6 presents summary information on the status of implementation and verification of each MPA. For each issue, the table shows the number of applicable plants, the number and percentage of plants that have completed implementation, and the number of plants remaining to complete implementation. For those issues requiring NRC verification of corrective actions, the table shows the number of plants covered by the issue, the number of plants at which verification is required, and the number and percentage of plants that have completed verification. Of the current 162 MPA issues,135 have been fully implemented,14 issues remain to be implemented at 5 or less plants and 3 issues remain to be implemented at 6 to 15 plants. The remaining 10 MPA issues are to be implemented at 19 or more plants. -

SAFETY ISSUE MANAGEMENT SYSTEM STATUS OF OTHER MPA(5) - SUPO4ARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED 47. 2 2 (100l 0 NO LOSS OF OFF-SITE POWER I 75 (B0891 68 68 (1001 0 NO SALEM ATWS 4.2.3 & 4.2.4 LIFE COMPONENTS B059 (E004) 13 13 (1001 0 NO BWR SINGLE LOOP OPERATION B059 (E005) 8 8 (100) 0 NO W N-1 LOOP OPERATION [' REVIEW OF OPERATIONAL ERRORS AND SYSTEM MISALIG999ENTS IDENTIFIED DURIN BL-79-06 56 56 (100) 0 No BL-79-06A 5 5 (100) O NO REVIEW OF OPERATIONAL ERRORS AND SYSTEM MISALIGNPENTS IDENTIFIED DURIN BL-79-08 5 5 (100) 0 NO EVENTS RELEVANT TO BOILING WATER REACTORS IDENTIFIED DURING THREE MILE BL-79-13 48 48 (1001 0 NO CRACKING IN FEEDWATER SYSTEM PIPING BL-79-15 107 107 (1001 0 YES 107 100 100 (1001 DEEP DRAFT PUMP DEFICIENCIES BL-79-27 60 80 1100) 0 NO LOSS OF N04-CLASS-1-E INSTRUPENTATION AND CONTROL SYSTEM BUS DURING CP BL-80-04 45 45 (100) 0 NO ANALYSIS OF A PWR MAIN STEAM LINE BREAK WITH CONTINUED FEEDWATER ADDIT BL-80-08 60 80 (100) 0 NO ENGINEERED SAFETY FEATURE (ESF) RESET CONTROLS BL-80-07 31 31 (1001 0 NO 8WR JET PUMP ASSEMBLY FAILURE RL-80-11 82 62 (1001 0 YES 82 61 61 (100) MASONRY WALL DESIGN i E NCE OF ADEQUATE M IMUM FLOW T CENTRIFUGA ARGING pup *PS F Table 5.6

5AFETY ISSUE MANAGEMENT SYSTEM STATUS OF OTHER MPAIS). SupmARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED 8L-87-01 107 107 (1001 0 NO THINNING OF PIPE WALLS IN NUCLEAR POWER PLANTS el-/8-01 107 107 (100) 0 NO DEFECTS IN WESTINGHOUSE CIRCUIT BREAMERS BL-88-02 33 32 (98 ) 1 NO STEAM GEERATOR TUBE RUPTURE (BULLETIN 88-02) (OLD MPA B099) BL-88-03 107 107 (100) 0 NO GE HFA RELAYS (BULLETIN 88-03) BL-88-04 107 108 (99 ) 1 YES 107 38 35 (92 ) SI PUMP FAILURE (BULLETIN 88-04) (OLD MPA 8103) to Ln BL-88-05 107 107 (100) 0 No NONFORMING MATERIALS SUPPLIED BY PIPING SUPPLIES, INC. AT FOLSOM 8L-88-07 35 35 (100) 0 YES 35 35 35 (100) POWR OSCILLATIONS IN BOILING WATER REACTORS (SW4S) BL-88-08 107 104 (97 ) 3 NO THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS BL-88-09 50 50 (1001 0 NO THIMBLE TUBE THINNING IN WESTINGHOUSE REAXCTORS BL-88-10 107 107 (1001 0 NO NONCONFORMING MOLDED-CASE CIPCUIT BREAMERS 8L-88-11 71 88 (95 ) 3 NO PRESSURIZER SURGE LINE THERMAL. STRATIFICATION BL-89-01 73 73 l100) 0 NO F AILURE OF WESTINGHOUSE STEAM GENERAT0it TUBE MECHANICAL PLUGS BL-89-02 107 107 (100) O NO STRESS CORROSION CRACMING OF HIGH-HARDNESS TYPE 410 STAINLESS STEEL BL-89-03 72 72 (200) 0 NO POTENTIAL LOSS OF REQUIRED SHUTDOWN MARGIN DURING REFUELING OPERATIONS BL-90-01 107 107 (100) 0 NO LOSS OF FILL-CIL IN TRANSMITTERS MANUFACTURED BY ROSEMOUNT Table 5.6

SAFETY ISSUE MANAGEMENT SYSTEM STATUS OF OTHER MPA(S).

SUMMARY

BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED BL-90-02 35 35 (100) 0 NO LOSS OF THERMAL MARGIN CAUSED BY CHANNEL BOX BOW BL-92-01 107 65 (60 ) 42 NO FAILURE OF THERMO-LAG 330 FIRE BARRIER SYSTEM 8L-93-02 107 98 (31 1 9 NO DEBRIS PLUGGING OF EMERGENCY CORE COOLING SUCTION STRAINERS i BL-93-03 32 24 (75 ) 8 NO RESOLUTION OF ISSUES REL TO REACTOR VESSEL WATER LEVEL INST IN BWR *S GL-79-25 17 17 (1001 0 NO INFORMATION REQUIRED TO RE"'iW CORPORATE CAPABILITIES e GL-19-32 57 57 (100) 0 NO TMI-2 LESSONS LEARNED TASK FORCE REPORT - NUREG-0578 GL-79-33 60 60 (1001 0 NO TRANSMITTING NUREG-0567-SECURITY TRAINING AND QUALIFICATIONS PLAN GL-79-36 62 62 (100) 0 NO ADEQUACY OF STATION ELECTRIC DISTRIBUTION SYSTEMS GL-79 i1 16 16 (1001 0 NO REACTDu' CAVITY SEAL RING GENERIC ISSUE (PWR) GL-79-46 62 62 (100) 0 NO CONTAINMENT PURGING AND VENTING DURING NORMAL OPERATION - GUIDELINES GL-79-55 42 42 (100) 0 NO ECCS CALCULATIONS 04 FUEL CLADDING GL-80-002 39 39 (100) 0 YES 39 36 36 (100) QUALITY ASSURANCE REQUIREMENTS REGARDING DIESEL GENERATOR FUEL OIL GL-80-024 64 64 (100) 0 NO MRC NUCLEAR DATA LINM (NDL) GL-80-030 60 60 (100) 0 NO CLARIFICATION OF THE TERM "0PERABLE* AS IT APPLIES TO SINGLE FAILURE GL-80-061 20 20 (100) 0 NO TMI-2 LESSONS LEARNED Table 5.6

SAFETY ISSUE MANAGEMENT SYSTEM STATUS OF OTHER MPA(S) - SUP99ARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED GL-81-01 52 52 (100) 0 NO ^ QUALIFICATION OF INSPECTION, EXAMINATIONS, AND TESTING AND AUDIT PERSO GL-81-04 63 63 (100) 0 NO EMERGENCY PROCEDURE AND TRAINING FOR STATION BLACKOUT EVENTS GL-81-14 42 42 (100) 0 NO SEISMIC QUALIFICATION OF AUXILIARY FEE 0 WATER SYSTEMS GL-81-21 72 72 (1001 0 YES 72 67 61 (91 ) MATURAL CIRCULATION COOLDOWN GL-83-08 21 21 (1001 0 YES 21 21 20 (95 ) MODIFICATION OF VACUUM BREAKERS ON MARK I CONTAIMMENTS GL-83-43 77 77 (100) 0 NO REPORTING REQUIREfENTS OF 10 CFR PART 50 SECTIONS 50.72 AND 50.73, AN GL-84-09 19 15 (78 1 4 NO RECOMBINER CAPABILITY REQUIREMENTS OF 10 CFR 50.44(C)(3)(II) GL-84-15 87 87 (1001 0 NO PROPOSED STAFF ACTIONS TO IMPROVE AND MAINTAIN DIESEL GENERATOR RELIA 8 GL-87 05 21 21 (100) 0 NO REQUEST FOR ADDITIONAL INFORMATION-ASSESSMENT OF LICENSEE MEASURES TO GL-87-12 70 70 (100) 0 NO LOSS OF RESIDUAL MEAT REMOVAL (RHR) WHILE IN THE REACTOR COOLANT SYSTE GL-88-01 35 33 (94 ) 2 NO NRC POSITION 04 IGSCC IN 8WR AUSTENITIC STAINLESS STEEL PIPING GL-88-05 72 72 (100) 0 NO BORIC ACID CORROSION OF CARSON STEEL REACTOR PRESSUllE BOUNDARY COMPONE GL-88-11 107 104 (97 ) 3 MO NRC POSITION 04 RADIATION DeRITTLEMENT OF REACTOR VESSEL MATERIALS AM GL-88-20 107 28 (24 ) 81 NO IISIVIDUAL PLANT EXAMINATION FOR SEVERE ACCIDENT VULNER. 10CFR50.54(F) GL-89-04 40 37 (92 1 3 YES 40 31 19 (61 ) GUIDANCE ON DEVELOPING ACCEPTABLE INSERVICE TESTING PROGRAMS Table 5.6

l l l i SAFETY ISSUE MANAGEMENT SY$ TEM i STATUS OF OTHER MPA(S). SUP94AR Y B Y ITEM IMPLEMENTATION VERIFICATION l PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED GL-89-06 93 93 (1001 0 NO l TASK ACTION PLAN ITEM I.D.2 - SAFETY PARAMETER DISPLAY SYSTEM GL-89-07 107 107 (100) 0 YES 107 106 los (100) POWER REACTOR SAFEGUARDS COTINGENCY PLANNING FOR SURFACE VEHICLE BOMBS GL-89-08 107 107 (100) 0 NO EROSION / CORROSION-INDUCED PIPE WALL THINNING GL-89-10 107 15 (14 ) 92 YES 107 107 26 (24 ) SAFETY-RELATED MOTOR-OPERATED VALVE TESTING AND SURVEILLANCE GL-89-16 22 21 (93 ) 1 YES 22 22 0 (0 ) h INSTALLATION OF A HARDENED WETWELL VENT (GL 89-16] GL-91-06 106 106 (100) 0 NO ADEQUACY OF SAFETY-RELATED DC POWER SUPPLIES (GL 91-06) (GI A-30) GL-91-11 107 107 (100) 0 NO VITAL INSTRUMENT 8USES & TIE BREAKERS (GI 48/49,GL 91-11) GL-91-13 14 12 (85 ) 2 NO ESSENTIAL SERVICE WATER SYSTEM FAILURES (GL-91-13) (GI-130) GL-92-01 107 87 (81 1 20 NO REACTOR VESSEL STRUCTURAL INTEGRITY GL-92-04 35 31 (88 ) 4 YES 35 35 16 (45 ) REACTOR VESSEL WATER LEVEL INSTP"JMENTATION IN BWR$ GL-92-08 107 35 (32 ) 72 NO THERMO-LAG 330-1 FIRE BARRIERS GL-93-04 49 0 (0 ) 49 NO ROD CONTROL SYS FAIL & WITHDRAWAL OF ROD CONT CLUSTER ASSEMBLIES GL-94-03 33 0 l0 ) 33 NO INTERGRANULAR STRESS CORROSION CRACKING OF CORE SHROUDS IN BWR'S MPA-A024 96 96 (1001 0 NO MISCELLANEOUS AMENDMENTS AND SEARCH REQUIREMENTS MPA-A001 61 61 (100) 0 NO 10 CFR 50.55 A(G) - ISI Table 5.6

SAFETY I$ SUE MANAGEMENT SYSTEM STATUS OF OTHER MPA(S) - SUPNARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED MPA-A002 62 62 (1001 0 NO APPENDIX I - ALARA { MPA-A003 59 59 (100) 0 NO SECURITY REVIEWS-MODIFIED AMENDMENT PLANS M*A-A004 47 47 (2003 0 NO APPENDIX J - CONTAINMENT LEAM TESTING MPt..A005 17 17 (1001 0 NO GE MARK I CONTAINMENT TECH SPECS-SHORT TERM MPA-A006 9 9 (1001 0 N0 E' RESPIRATORY PROTECTION SYSTEM MPA-A007 11 11 (1001 0 NO APPENDIX G. FRACTURE TOUGHNESS MPA-A005 8 8 (1001 0 NO ECCS EVALUATION-GENERIC PER 50.46 COMPLIANCE MPA-A008 58 58 (1001 0 NO PRESSURE VESSEL SELTLINE MATERIAL SURVEILLANCE MPA-A010 80 80 (100) 0 NO CONTINGENCY PLANNING MPA-A012 57 57 (100) 0 NO VITAL AREA ANALYSIS MPA-A014 48 48 (100) 0 NO 10CFR 50.55 A(G). INSERVICE TESTING MPA-B116 35 31 (88 1 4 NO RESULTS OF NRC TESTING OF MOVS (GL 89-10. SUPP3) NFA-8117 72 70 (97 ) 2 NO FAILURE OF WESTINGHOUSE SG TUBE MECHANICAL PLUGS (BL 90-01. SUPP21 MPA-Bilt los 3 (2 ) 103 NO IPE EXTERNAL EVENTS (GL 88-20. SUPP 4) MPA-B122 107 40 (37 ) 67 YES 107 107 5 (4 ) LOSS OF FILL-0IL IN TRANSMITTERS MANUFACTURED BY ROSEMOUNT Table 5.6

l i l SAFETY ISSUE MANAGEMENT SYSTEM STATUS OF OTHER MPAIS) - SUPMARY BY ITEM I I . ff................... f I PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED INACCURACY OF MOTOR-OPER. VALVE DIAG EQUIP (GL 89-10 SUPP 5) MPA-B124 34 19 (55 1 15 MO DEBRIS PLUGGING OF ECC SUCTION STRAINERS (BL 93-02. SUPPL 1) l MPA-8001 25 25 (1001 0 NO i DIESEL GENERATOR LOCMOUT MPA-8002 55 55 (1003 0 NO FIRE PROTECTION i MPA-BCO3 38 38 (1001 0 YES 38 34 34 (100) l g PWR MODERATOR DILUTION 9 MPA-8008 20 20 (100) 0 NO ( BV1t RELIEF VALVE MPA-8007 24 24 (100) 0 NO STEAM GENERATOR FEEDWATER FLOW INSTABILITY MA-8008 15 15 (100) 0 NO PWR HPSI-LPSI FLOW RESISTANCE l MPA-8009 17 17 (1003 0 NO CHARGING EYSTEMS PIPE VIBRATIONS MPA-8010 3 3 (2003 0 NO l BURNABLE POISON ROD FAILURE - B&W l MPA-0011 9 9 (1001 0 YES 9 3 1 (33 ) 1 l FLOOD OF EQUIPMENT IMPORTANT TO SAFETY MPA-B012 11 11 (200) 0 NO ( STEAM GENERATOR TUBE INSPECTION MPA-8013 10 10 (100) 0 NO FUEL ROD BOW MPA-8014 3$ 35 (2003 0 NO CEA GUIDE TUBE WEAR MPA-8015 g (100) 0 NO C-E POISON ROD GROWTH l Table 5.6 i

SAFETY ISSUE MANAGEMENT SYSTEM STATUS OF OTHER MPA(S) -

SUMMARY

BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED MPA-B016 62 62 (100) 0 NO EMERGENCY PLANNING AND REVISIONS MPA-BOIS 2 2 (100) 0 NO WORTHI4GTON RHR PUMP SHAFT INTEGRITY MPA-B019 2' 2 (100) 0 NO NEUTRON SHIELDING - CE REACTORS MPA-8020 $7 57 (1001 0 NO CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION e MPA-B021 57 $7 (1001 0 NO {^ LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF AhMUNCIATOR SYSTEM "f MPA-B026 36 36 (100) 0 NO INADVERTANT SAFETY INJECTION DURING C00LDOWN MPt-8027 20 20 (100) 0 NO REVIEW RESPONSES TO IE BULLETIN 78-03 (OFFGAS EXPLOSIONS) MPA-B029 5 5 (100) 0 NO BWR FEEDWATER PUMP TRIP MPA-8030 5 5 (100) 0 NO STE AM GENERATOR REPLACEMENT PROGRAM MPA-8032 23 22 (95 ) 1 NO BLOCKED SI SIGNAL DURING C00LDOWN MPA-8034 1 1 (100) 0 NO BWR JET PUMP INTEGRITY ASSURANCE MPA-8035 5 5 (100) O NO ORIFICE R00 ASSEMBLY INTEGRITY - B&W MPA-B036 7 7 (100) O NO RESISTANCE TEMPERATURE DETECTOR (RTD) RESPONSE - CE MPA-B037 9 9 (100) 0 NO STEAM GENERATOR TUBE DENTING AND SUPPORTPLATE MODIFICATIONS - CE MPA-8038 2 2 (100) 0 NO TENDON SURVEILLANCE - BECHTEL CONTAINMENTS Table 5.6 ma

SAFETY ISSUE MANAGEMENT $YSTEM STATUS OF OTHER MPA(S) - SUD94ARY BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED MPA-8039 36 36 (100) 0 NO PWR PRESSURE - TEMPERATURE LIMIT TECH SPECS MPA-8040 1 1 (100) e NO DIPE SUPPORT BASE PLATES MPA-Boel 63 63 (1001 0 YES 63 60 59 (98 ) FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER SUPPLEMENTS) MPA-B046 51 51 (100) 0 NO ANALYSIS OF TURBINE DISC CRACKS e MPA-8049 11 11 (1001 0 NO g PWR CONTROL ROD MISALIGNMENT MPA-B052 27 27 (100) 0 NO REVIEW OF SAFETY ASPECT OF INADVERTENT SAFETY ACTIONS DURING SUR TEST MPA-8055 5 5 (100) 0 NO B&O REPORT ON BWRS MPA-B056 6 6 (100) 0 NO CONTROL RODS FAILURE TO INSERT. BWR MPA-8057 31 31 (100) 0 NO DHR CAPABILITY MPA-8064 7 7 (100) 0 NO ACC INDUCED FLUX ERRORS (B&W) MPA-8067 8 8 (100) 0 NO THERMAL SHOCK MPA-8070 42 42 (100) 0 NO FATIGUE TRANSIENT LIMIT TS MPA-8073 7 7 (100) 0 NO PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITERION MPA-8074 4 4 (100) 0 NO THERMAL SHIELD FOLLOW UP ANALYSIS MPA-C006 34 34 (100) 0 NO PUMP SUPPORT-LAMELLAR TEARING TalHe 5.8 .m

SAFETY ISSUE MANAGEMEN T SY STEM STATUS OF OTHER MPA(S) - Simt4ARY BY ITEM IMPLEMENTATION VERIFICATION ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED MPA-C001 35 35 (100) 0 NO PWR SECONDARY WATER CHEMISTRY MONITORINGREQUIREMENTS l MPA-C002 19 19 (100l 0 YES 19 19 19 (100) { BWR-RECIRC. PUMP TRIP (ATWS) MPA-C003 15 15 (100) 0 NO QUALIFICATIONS OF RADIATION PROTECTION MANAGER HPA-C004 16 16 (100) 0 NO FILTER TECH SPECS b MPA-C005 8 8 (100) 0 NO O CONVERSION TO STANDARD TECH SPECS G3 MPA-C007 38 36 (1001 0 NO FUEL HANDLING ACCIDENT INSIDE CONTAINMENT MPA-C008 9 9 (100) 0 NO BWR POST LOCA H2 CONTROL MPA-C009 7 7 (100) 0 NO PWR AUX FW PUMPS MPA-C011 20 20 (100) 0 NO RPS POWER SUPPLY b LUBILITY DURING LO G TERM C00LIN FOLLOWING A MPA-D002 21 21 (100) 0 NO ECCS ZIRC CLAD MODEL ERROR-COMPLIANCE WITH 10 CFR-46 MPA-D003 16 16 (100) 0 NO I PRESSURIZER HEATUP RATE ERROR MPA-0005 6 6 (100) 0 NO PLANT UPI MODEL PROBLEN MPA-0006 6 6 (100) 0 NO PEAMING MODEL CHANGE FOR CE REACTOR CORE MPA-D007 3 3 (100) 0 NO SWR POWER LEVEL FOR RWM Table 5.6

b i SAFETY ISSUE MANAGEMENT SYSTEM i STATUS OF OTHER MPA(S) -

SUMMARY

BY ITEM IMPLEMENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLANTS PER CENT ITEM APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED COVERED REQUIRED COMPLETED COMPLETED MPA-D008 3 3 (100) 0 NO DEFICIENCY IN CHEM ADDITION TO CONTAINMENT SPRAYS l MPA-D00? 1 1 (100) 0 NO GE ECCS INPUT ERRORS MPA-D011 57 57 (100) 0 NO FISSION GAS RELEASE b. MPA-D013 6 9 (100) 0 NO B&W SMALL BREAM ERROR MPA-D014 9 9 (100) 0 NO 1 REACTOR VESSEL WELD - WIRE DEFICIENCY o 36 MPA-D015 59 59 (100) 0 N0 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAILURE s MPA-0018 7 7 (100) 0 NO NUREG 0630 CLADDING MODELS (B&W PLANTS) MPA-E001 28 28 (100) 0 NO SPENT FUEL POOL EXPANSIONS [ MPA-E002 7 7 (100) 0 NO j FUEL CASK DROP MPA-E003 28 28 (100) 0 NO I CORE RELOADS REQUIRING PRIOR NRC APPROVAL MPA-E006 7 7 (100) 0 NO CEA POSITION INDICATION FAILURES - CE MPA.Ec07 5 5 (100) 0 NO REACTOR PROTECTION SYSTEM LOGIC - CE i, h I Table 5.6 l ~ _...,. _

i 5.5 Conclusions t l After a detailed review of the implementation and verification status of the resolution of the 162 MPAs, the NRC staff has concluded the following: o The NRC closure for P *, pas is adequate to protect the public health and safety. e Licenseas are making progress toward implementing MPA-related actions requested by the staff, and the framework exists to oversee future implementation actions associated with those MPAs that have been resolved.

Progress is bein0 made in verifying the completion of implementation actions associated with those MPAs that have been resolved.

The NRC staff will maintain close watch over implementation actions and schedules proposed by licensees to ensure that they are completed in accordance with regulatory requirements. j -105-n.

t l F Appendix A { LISTING OF t UNIMPLEMENTED TMl ITEMS BYISSUE l i l l l i I i ) i l l 4 i l A

1 l APPENDIX A ) This appendix provides a detailed list, by issue, of the 11 TMI Action Plan items na: implemented, along with the projected target date for completing the item. Status and projected implementation dates are presented as of September 30, 1994. l l I 1 A-1

I b I A-2 ~ __ __, ~----'--'------.-._____

i f l (W. 22222988822 sssssssssss ~* $88G888GC$t l 22, 238 EE WWS RR: - $aaaaaaayy~2233333 1 JJ58888888 y1111111 88c i --22 8666688 l un'ettette i Ef 2222 2 2 2 ~$$$$$$$ g u u m C D E D. 5 5 5 e33...

-.B S.

I 5 2B "BE 88

:.g g = = g g g y E.!!.85555555 e.

SSSSSSS ygg 22 stud 5 e .ss

~~:EEEEEEE B

.m~~~~~~~ 99daassaas .t

adididid

~ g 8:: Jacaded MRGRg2R"RRC $553,3GGGGG u affffffffff 5 l""W5Wg5" 5Ed-E Y"~l5Id.E.tBI' 5 gog*EE"* y t 55 .E r .s g22Rccccccc .2222222222

- - hcCCCCCC

".*942222222 1 I a ' '. ; a a a a a a a

tttttk&

JAAdAddeidi i l A-3 1

l A-4

Appendix 8 LISTING OF UNIMPLEMENTED USlITEMS BYISSUE

APPENDIX B This appendix provides a detailed list, by issue, of the 105 USl items not implemented, along with the projected date for completing the item. Status and projected implementation dates are presented as of September 30,1994. B-1

A m-a A. k- .L --s---. f f s I 9 ? k I I I y I i l l I B-2 P k ~v m

t*wtwt wert %atety Isttsen (t ht 6cy cf Otwei Itrent twt 155 tit wA l't Auf TAC ititt Datt 1. A 31 5004 WA00AM utta MTT02% owa Snuttual et0UtytMtu15 94/10 2. A 44 8022 Aet Au5A5 1 Mh850ft twitMtut At ttue of INE Stalgou et Att0ttt 9 tat 10 tra 50.63 95/06 3. A && A022 AetAuSA5 2 seg!$09 IMrt tMe m1 A1304 Os TMt 51 Allom Rt Artout eutt, 10 tte 50.63 95/12 4 A-te A022 SIG #0tt P0tui se68514 twtIMfu1Alleu 08 tut St Attrue et Art 0UT NUtt,10 Cf t 50.63 96/10 5. A-64 A022 (ALVt91 ttIFf5 1 8e68525 lettMiu1AltOu of IMt 51 All04 StetttU1 Dutt,10 tre 50.63 96/95 6. A 64 4022 C8tVIRI ClitF5 2

- Mf526 l etIMfutAllou 08 Int 5f atION Rt Att001 outt,10 tra 50.63 96/05 7.

A 64 A022 GluuA M68548 t wtIMtulattou of f ut Stat tom et Att0UT Putt,10 Cf t 50.63 94/12 8. A 44 A022 mA00AM utta pe68551 pirttMtu1AtIOu os tut STAllow at Act0UT putt,10 CfR 50.63 95/06 9. A-64 A022 luDIAes P0 tut 3 te68557 tet t Mt u1 At t om of tut STATION 81 Att001 Dutt,10 Cte 50.63 96/12 ) 10. A 44 4022 MDutitttto M68569 IMrtIMEu1Atl04 of INE STAT t0m Bl4Ct001 etRE,10 (fR 50.63 96/12 11 A 46 A022 u0 min Asum 1 peM1572 IMettMtu1 Attom os sur 51Allou et Att001 eutt,10 Cte 50.63 94/10 12. A-64 A022 uCRiu AeMIA 2 MMI573 twtIMfatAttou of THE ST Allou 81 Att0U1 #Utt,10 Cf t 50.63 95/06 13. A-64 A022 PAto virot 2 M68580 tellMtu14110m os int stations siett0Ut eutt,10 Cfn 50.63 95/06 14 4-64 A022 PtAtu 901 TOR 2 te68582 twt f ututA110m or THE Statlose St Attout evtt,10 tra 50.63 96/10 15. A-64 8022 PE ACH 9011tre 3 pe68583 18ert f Mt u1 Allose 08 iMt 51 Allom St AttOJ1 RUtt,10 CFR 50.63 96/10 16. A 44 4022 OUA0 Cittts 1 M68590 18ert t ME u1 Al tose et 1ME 51At tou Ot Att001 #Utt,10 Cta 50.63 95/12 17 A 44 A022 OUA0 Citif S 2 tem 1591 ImrttMtutAllou 08 THE $1 Af fou et Attout eutt,10 Ctt 50.63 95/12 18. A 44 A022 Sam anotet 2 .se68599 IMet t ut ut At tou et iME ST At tom et Att0UT etRt,10 ttt 50.63 94/10 19 A 64 A022 5A81 Omotet 3 M68600 18ert f Mtu1 A110m of 1ME 5 tat 30s Bt Att0U1 tut t,10 Cf R 50.63 96/10 20. A-44 A022 St000 fan 1 peMI603 IMet tsst u1 Alf 0's of 18st ST At :04 St Att0Ut etM,10 Cf R 50.63 95/12 21. A 64 8022 SEOUDYAu 2 9468604 IMett8stu1 Attone or int St At10m Mt Att0U1 Dutt,10 CfR 50.63 96/12 22. A-64 A022 SupWY 1 pe68611 twi t tat u1 A110m 08 feet Stattom et Attout evtt,10 tre 50.63 96/01 23. A-64 A022 Sut#7 2 M68612 IMettMtu1Att0m of THE STAf ttWe Rt Att001 etRt,10 Cta 50.63 96/05 24. A 64 A022 WAtterop0 3 M68623 IMrs testu1Atlose 08 IWF Stallow pt Att0UT Rutt 10 Cta 50.63 96/12 25. A-64 A022 Wup 2 M6M626 IMetIMEuTAttou of t'st ST At taus et ACR001 Butt,10 Cr# $0.63 95/09 26. A 46 8105 8etAu5A5 1 M69426 5t15Mit OUAtIfICAttone (Gt 87-02) 95/07 27. A-66 9105 AttAu5A5 2 M69427 5815Mit 00At tiItA110u (Gt 87 02) 95/07 28. A 66 8105 SEAvit valtET 1 M69628 Sil5Mit Opallf tCAllon (Gt 87-ft?) 95/0F 29. A 46 9105 glG poca Polut M60429 sf IsMit 0081If t[At t04 (Gt 87 02) 95/97 30. A-46 5105 goonats ifRRY 2 te69431 5815Mit DUAt titCATIces (Gt 87-02) 96/97 31 A 46 9105 99UuSWitt 1 M69633 stI5Mit ount IfitAtton (Gt 87-02) 95/96 12. A-66 e105 peUusvita 2 se69634 5ttsnit ovattiICA1104 (GI 87 02) 95/10 33. A-46 8105 Calviti tilfts t su69435 tituelt OUAt ttttAttose (Gt 87-023 96/97 34 A 46 5105 CAtvtal Clift 5 2 se69636 5t tsMIC ovatittCAf t0m (Gt 87 02) 96/92 35. A 46 8105 C00Pfe STAttOne se69439 StisMIC ouAt tilCAttou (Gt 87 02) 95/07

36. A 66 8105 tavstat alvte 3 Mr.9440 M twit ovai tt itatION (Gt 87 02) 95/12 37 A 66 5105 0 t tact 1 M69617 si lwit cUallittatten (GL 87 02) 95/07 38. A 66 5105 ft t COOK 2 m94 W 13 twit oust It it Atttet (Gt 87 D/) 95/07 39 A 46 8105 Davls-stsst mv441 sp Isnts ovat leitAtION (GL 87 07) 95/09 40. A-66 B105 retsDtw 2 m9447 sf lutt onAt is itATIOu (Gt 87-07) 95/11 61 A 66 8105 t#tsDtm 3 M69441 si t wit oVAt li stall 04 (Gt 87-02) 95/11 42. A 46 8105 DUsut aa4010 M694&4 St Iwlt 00A6 It ttAt ton (Gt 87 02) 95/11 43. A 66 8105 tartti 1 M6944*- si tt.Mit cVAt it ICATION (Ct 87 07) 95/05 44 A-46 9105 ItilPATRitt M69446 si f AMit ovat toICAtlow (Gt 87-02) 95/05 45. A 66 8105 FURI CAtNOUM 1 M696&T setsMit OUAtitttAft04 (Gt 87 07) %/07 46. A 46 BIOS Gewma M69469 st isMit avai ttitATIOu (Lt 87-02) 95/05 47. A 66 9105 ma00AM utta M69450 st twit oVAtititaticu (Gt 87-02) 95/12 48. A 46 8105 DAftn 1 M69651 stIsMit 004 ItICAtlau (Lt 87 02) 95/06 49 A-66 9105 mattu 2 M69457 st IsMit cuat tiltat104 (GL 87 02) 95/08 50. A-46 5105 1408A4 Polut 2 M69453 te isMis oVAa ltitAttou (Gt 87-02) 95/11 W 51 A 66 5105 tuDIA# pot 41 3 M69454 st 15Mit cuallf f tAttou (Gt 87 02) 95/11 h 52. A 46 B105 trua04tt M69455 sil5Mit coatIslCAf tom (Gt 87 02) 95/11 53. A 66 8105 Mittsitzt 1 M69458 st isntt CUAt tr itAt tou (Gt 87-02) 96/10 56 A 66 8105 MittsTONE 2 M69459 st 15Mit ovat tricAtl0N (Gt 87 02) 95/05 55. A 66 8105 M0411cEtt0 M69460 st 15MIC cu&tIfitAtton (Gt 87 02) 95/11 56. A 46 0105 41NE Mitt PotNT 1 M69461 sE ssMit OUntititA1104 (Gt 87 02) 95/05 57 A 46 e105 isonen Awwa 1 M69462 st lsMit ount Irltailou (Gt 87 02) 9'/12 58. A 46 0105 WOR 1M AWWA 2 M69463 st IsMit OVAL tittAtt04 (Gt 87-02) 95/06 59. A to 8105 otourt i M69464 tt Iwit ovat IfICATIon (Gt 87 07) 95/06 60. A-66 8105 0004tt 2 M69465 st1 wit oVAtItICAtIOu (Gt 87-02) 95/06 61. A 66 8195 000Ntt 3 M69466 sil'Mit OVAL 19 f tAIION tGt 87 02) 95/06 62. A 66 8105 Ovstit tettt 1 m9467 st ISMit OUAt tistAt:0w (Gt 87-02) 95/09 63. A 46 8105 PatisADES M6946R st tsmit cuat Irltat:0u (Gt 87 02) 95/07 64 a 46 9105 Pt Acn 30f t0M 2 M69469 sil'Mit cVAtIfttAtt04 (Gt BT 07) 95/11 65. A 66 9105 PEACM 90titPI 3 M69470 st ISMIC OUAt It ttA1104 (Gt 87 02) 95/11 fe. A-66 5105 PitGRIM t M69471 st ISMit OUnt ititAtt04 (Gt 87-02) 95/11 67. A 46 8105 Potut 9EACN 1 M69677 stismit oualitttAtt04 (Gt 87 02) 95/06 68. A 46 8105 Polut stAtti 2 M69473 st isMIC OUAt tt ttA110m (Gt 87 02) 95/08 69 A 46 5105 PeeltlE ISLAND 1 M69474 stisMit ountititAttom (Gt 87 02) 95/11 10. A 46 8105 PWAtRIE istAND 2 M69475 stisMit OUAttricAtt04 (Gt 87-02) 95/11

T1. A-66 8105 Otmo Citif5 1 MA94 76 %Il%Mit alAt ititallou (GI 87 07) 95/11 72. A-46 5105 OUAO Clfits 2 M69477 stitMic coattritAttom (Lt 87 D/ t 95/11 73. A-46 STOS e0Hlus04 2 M69678 %II9 tic 008t ititAil04 (Gt RT 07) 96/12 74 A 46 5105 5Attu 1 M69479 sil5Mit cuattricAllou (64 87 O/> 95/11 75. A 46 8305 SAttM 2 M69680 St1%Mic ostatifICAtlau (Gt FF (17) 95/11 76. A-66 B105 51 tUtil 1 MA9683 St itMit 3)At itlCAttuu f Gt 87 07) 95/06 77. A-46 8105 $ Uter 1 M69484 silvelt ouAtivitAllou (La 87 07) 95/11 78. A 6A 8105 $Ur#7 2 M69485 st15Mit cuAtilltallow (Gt 87 07) 95/11 79 A-46 8105 turtt Mitt ist AuD 1 MA9686 stI5Mic ovatitICAf fou (Gs 87 07) 95/12 80. A-&6 8105 ttatt? Polut 3 M6M303 sllsMic ovettettATIOu (64 87 01) 95/06 81 A-46 9105 tunttY solut & MA8304 5t 15Mit OuatItICAi10m (Lt 87 01) 95/06 82. A 66 8105 vioMout Teestit I se69690 stisMic coalititAllum (Gt 87-07) 96/03 83. A 46 8105 Flom 1 M69692 5tl5Mit o#Atit ttAttou (Gt 87 02) 96/11 84 A 46 B105 fices 2 Mn9493 stisMic ouAtitstAttou EGt 87 07) 96/11 85. A-47 5113 Attausas 2 M749f" tr5 t 4 47, sat t 1T ISEPtIC At t 045 08 00u1#0L Sv5ftM5 (GL 89-19) 95/06 [ 86. A 47 5113 CAtytet Ct1985 1 M16923 1751 4-4 7 SAttif IMPtl Call 0NS Of t04tt0L STsitM5 (Gt 89-19) 96/10 ( 71 87 A 47 9113 CAtytet Ctlits 2 M74976 USI A 4 7, SA t t if IMPittAtlDuS Of coutP0t ST5ftM5 (GL 39-19) 94/10 88. A 47 8113 (00 Pts ST ATION M16932 1758 A 47, 5Artiv IMPtitallou5 Of Controt STsitMS (GL 39-19) 95/01 89 A 47 5113 Ort $0tu 2 M74937 USI A-47, 5Af t t? 8MPLICAlleus 08 *oest*0t ST5ftM5 (Gt 89-19) 95/01 90. A 47 8113 Def 50tu 3 M74938 IKI A-47, 58FitT n,*eICAllous Of toutect ST5ttM5 (Gt 89-19) 95/01 91. A 47 9113 titTPAtettu M16943 1758 A 4 7, SA F E T T IMPt r.Ats0us 06 C01strot ST5ttees (Et 89-19) 95/04 97. A 47 8113 8081 CAtuCUm 1 M76944 15l A 4 7, 5Af t t T IMPtitAllDus M tou190t 575ftMS (Et 80 19) 95/05 93. A-47 5113 mattM 1 MT&969 LF5I A 47, 5Artt? IIs't tcA110ms 08 00eefect SYSitM5 (61 89-19) 95/12 96 A 67 88113 mattu 2 M74950 tr5I A-47, tart tT IFPt itAll0NS 08 004t#0L %f51EM5 (Gt 89-19) 95/12 95. A 67 9113 Mit t S104t 2 M16963 U51 A 47. t Att iv IMPt it A110ers et routp0L ST5tt.o (Gt 89-19) 95/03 96. A 47 3113 OT5tte cattu 1 M 74973 tlst A 47, %Aff tv IMPtitailows 08 tout #0L ST5f tM5 (GL 89-ft n 94/12 97. A-47 9113 pat l5ADE S M14974 tt51 A 47, %Artif 18'Ptif Allows N toultot ST51tMS (Gt 89-19) 96/12 98. A-67 8113 PtAces 90170M 2 M T&97M If51 A-47, SAf f IT 19EPtItaij00ft es Irugit0L ST5ttMS (GL 89 19) 95/09 99 A 67 8113 PIAtu 90tt0M 3 M 74979 LFI A 47, 5ArttY 18EPt Itatt0u5 De t outpot 5751tMS (Gt 89-19) 95/12 100 A-47 8113 Pitcelm 1 M74981 test A-47, SAtt ti 18PitCAttous tu tout #0L ST%ltM5 (Gt 8919) 96/12 101 A 47 9113 5Au ouotet 2 M1AS94 ttsl A 47, %Attiv IsPtitAtIOus Os toutrot 5751tMs (GL 89-19) 96/12 102. A 67 5113 5Au omotet 3 M14995 tr51 A-47, SAttif IMPt1CATIDES Os tout #0L SYsitMS (GL 8919) 96/ J 103. A 47 5113 UAlter0ND 3 8975016 1751 A 47, 5Attif IIIPg $tAttou5 Of t04190t SYSitMS (GL 8919) 96/11 104 A-9 A020 DetSDtu 3 M59090 to tre 50.62 OPteattuG etAttee etvitv5 96/10 105. A-9 A020 OUA0 Cittts 1 't">9132 10 tre 50.62 CPteAtleG et At 09 etvitv5 96/10 - - - - - ~ ~

l B-6

.~ 1 l Appendix C j LISTING OF UNIMPLEMENTED GSI ITEMS BYISSUE l i l l I ) i

i APPENDIX C This appendix provides a detailed list, by issue, of the 63 GSI items not implemented, along with the projected date for completing the item. Status and prcJected implementation dates are presented as of September 30,1994. 1 i I i C-1

._.._m I l T \\ a l 1 i I c-2

f. ~;2~222: : 8282882:~2: : s~222e222:225 ~~~~~ ~~~ss s sss s ss ss s ssss s ss ss s s s ss s $3838833;.88888 Gstst';GtstsstiststG ~* .a s.a.a a.a s a a s a.a a a a a a 5 5= 555=====5------------------

=

BeeEeEeeeeeEEEEEe888888888888888888 vww wwwww wwwwwww ww WWWWWrert:W*Wrrrussssssssssssssssss .= =.=.= ....... s. s s. s. s. s. s. s. s s. s. s s. s. s s s. a .= = BBEsssssssssBassa::::::::::::::EEEE f aumammumm==mammuse============ cccc E * *s * * ! * *e *= *e 5. 5

E E *s *

: : : : : : : : : : :- : :e :o :o :e e

e e es e-- dwwwwwwwww w w --------------.... w www w w w w w w w w w w w w w w w & & & & rrrrrrrrrrrrrrrrr,===========*=w a w w w BBBBBBBBBBBBBBBBBrrrrr.rrr.rrrrr,e,s.gg ,,,,,,,,,,,,,3g w ww w g gggggggggggggg.ttt s.s.s.s s.s.s.s.s.s.s.s.s.s .s.s.s 9999*B999999*B9**55555:n55mszz58888 EEEEEEEEEEEEEEEEE 99999999999999ttti l f E5555555555555555){g[=Eppppppppg!BBB rrrrt5rrrrrrrrahrtRRRRRRRRRRRRRRitts Ettss.sc?s sstr w

7;;;;;;;23;;;;;;;;;;-

E E 3 3 3 3 E E E E E R 3 E E E E + sh @ @ en en ef-d- .h d f f @ e @ @ @

aaaaaaaaaa'Waaaaaaaa th

= %mN o ~ EAA$-md5ggggS3 cE4Ek$~EEE*g<:2gre~~eg - rc. - esu A* 4 000?mm mmm. tett tett::tetteet kiknikkkkkkki:kikke aaaaa: x: ara y - m - ~ >E -N ~ ~ - ~ ~ -5.. 5: 5-2"* ess g*if-mii 5 w ww- ~ ~ -- ~ -- -~.::gO::ss-is y w w- - ~ s... .ur- ..~ In s.--ew WW E. r r I-tr. --e== r. , g,w -.3-N g33--- g w r sw s=!!

- EB 33 255583WWEII

$$.W53 N ~~~~~~~~~~~~~~~~~..............eer, N N NNEN N

b. O.O. O. O.

O. O. O. O. O. O. O. memeeeeeeeeeeeemme i O O O 1 .C O ) "9"9"99"9999"99* y mmmmmmemmmmmmmmmm acaaaaaaaaaaaaaaaRRRRRRRRRRRRRRio.tt m eeeeeeeeeeeeeeese d -b d N e - - - - - - - -- NN N N NNN -M M mmm C-3

~ - ~ ~~~ co-oo~~E~tttttttttttttted --~~--.~~~~~~- tttttttttt $88888G8$$$GG8888GG8888$$$G$ I I l r E l 6$6268.E E5..:.:.::.::.:.:.:.:.:: l ..ggggggggggggg 888888J 3 3 3. 3 3 3. * - - - - -.y *

: : : : : : : : : : =

I............. i o...........-- h <<<<< ww w w w w ww ww =w EEEEEE# ~ ~ ~ ~ ~ g g w-5 E E E E E - M. E. M. E. M. M. M. M. M. E.. :.. ~~ Efff((* 3333-~rrrrrrrrrrrry-53 -~~EE3333333333333 I 8fifff33 g--5$stf"::BB88:::::5:88555: fffffffffffff l 755 OC"000f[222t((tttttttttttit885 888 8 u

2tttt
- - - - jxxnnxEE

$$$$$$.'==CCCC;;

samaman E

1

=

srans C ktttti......rr000..*00**f00005

r;;;;E:

2.............i ~ 888888..h.h!b.h"83" ~-~-- 3 i yyy:yygS**** 5555555555555e i -w BB E + E E g g g. . e. r. M. M. M. e. r. t. r. e. s i .. E, r w

<w

+ + 5555555 mumsmssassa3st -w oe---..-<po - -- epe-g m4N A m ~ ~ m< oc~ ~e e m m # e # # m eec% A A > >>BB EN N N $ck E DDDDINg ( cco ECE ERraaar(s ddddNNdS w aa: aa: a aa a arr b

~

. M N M W I

~

t N> w ~ a UI:g-- w - + -~Eji-r'.".r*w. - UU-*a I.w~rE25-r_t

w..-

. re.. g ~~. 50hI,r__,Es_r~~$gw m 33.NE ge ~ $ 5 sS. 33rw a trgII 1 w w attr;3t&555 tygggig.

##ercessussummmmmmmmmmmmmmm

=

- e C 00 0 0 *
  - - - N
e e e * *
- - - - W W FPD D P D PD P DO @ @ @

esasme aseemw w w w ww ww w w ww w ww e a ? $ < < < < < n u m m m m. m m. m m m. m...mmm m e--. ~ o E. E E. E. E. E. E. E. E. E. E. E. E. E. E. E. E. E E E E ". 8$$888333333333333333333333k $'mmma<n'AJidadi&J4AJJiada8'ee;e aissa 'd <<<<<<<< ecee +++++e C-4 i I

l i l l Appendix D LISTING OF OTHER UNIMPLEMENTED MPA ITEMS BYISSUE l _ j

t APPENDIX D l This appendix provides a detailed list, by issue, of the 644 MPA items not l implemented, along with the projected date for completing the item. Status and projected implementation dates are presented as of September 30,1994. l i i D-1 i

i i l I I 1 l i ) i I 1 i 1 t i I i D-2

t F }

t.:sase222~e22ssseo :

r 26s22~~e.822. SCGtstGt: GEE;'C';G88885G338888888:~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~: ^ ~ .ub b 0% ~

e. e. e.

ttt .oass

=

8 8 8.:..:.:. I EE!s.s.i. o 8 -rrearr -ooeo_-- ~ ----

=

ccesss t *n : : = s.e t a s 1-o 1; e e a t 111ococco=ococococococcocoocco .t WWg Eg'.:.tggg.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~.~. ~ s--- t

$50:::s,.a..

a. E E a,,

, E <g < -,,.,..,.,,,,- - _..--- -- a.a. E,aI

.Eg siWga

gggI, g-i g

I;5&iliittitittiittit.i._t_iitii_z_istitt 3 i 3IrIIII.i.EEEEEF.F.E^Et.^^6IIIfifffF.F.Fi.f*66 k~~3 l I III r.rrrrrrrrrrrarrrrrrrrrrsrrrrrrrrr

a. a r

A - ~~ e - m as, G E, c g - r E EE- - -, F R F, & gro ~ ao-~<~em. ~ c g ~e E 2 2,, -ce EE3G c= 2- .R. '8 r -.e. - m. ~~~--. w E litittayEfffffffffftFffftiffiifffff - ~ W - N N - ~ gg-o gg-~

~~-~::

5 E E-~ .I t .,"g5 22-~s85*$**

== gzu~ . ~ - ~ I.t**r... B. A ! : 5., 3_ "t r - - o. 8

- se,$

....B.,r,- w . vs-. w r r _...n. e.. - g sa sa seeae=we5 a.- - a , o a yy --.------e y EEEEERRRRRRRERR.RRRRRRRRRRRR.RRRRR [ ER N N K E N N N N > m M N N N M h N M N > K N N N N E B 3 M N M M N E8EEE. -.---ooooooooooooooooooooooooooo e66e6ecw4k4444444444444444444444444 mE E m, KcK &. P, D P O. P. O P. P. O P. P &. & & P P. D D D D & O. O. O. P. P. o# N [ h.o. *.b. [ .d. b. N. h oP b N. O b h e m.b m.4$ -bN [ hb E .. - tw gw N % rw N rw N g, tw a 6 m D-3

I

:~~: :EEEE~~~

:: : E

.:::ee~:: ~~~~~~~~~~~~~e ~~~.s~ss: ~~~~~~~~~~~~E~~s ~~~~

:ss.;ssssssss:ss ss

s;sassssats

EEE s=ssesse:

INEEEEEggg rrrrrrrrrE 22:::::sserererer $$$$$$$$$BBBBsBBB 88!8888!!"ddd.dddd;;; rrr. rrrer N N s s W W s N s u s.s a.u s s a r e,s _t _e _t t _t t _t t _i lill! aa EEEEEEEEErzzzzzzzass we. EE.... ..ssssssssere s s s s s s s : : : : : : : : g= r= g= -w-ww www-: :::::::

=======zE EE?BEEEEEEEEE55*!55.I.55*IIIIIIIIBBB

5

~. ~. ~. ~ ~ ~ ~. ~. ~ ~. ~ ~ ~ ~ ~ I.. ..I--------rrr l zzzzzzzzzzzzzzzrrrrrrrrrrsssssss ~~-----

ssssssssa-ss-s---::

ss s rs.r= g55EgE555ggggggtreittigt

2c s _i _s _s _t _s _e _s s e _t _t s _e _s.5 3 g a g g g q.......

0 0 0 A r. r.=._._ : t = =s : = =s =s =s =s - - - s s err e f f f f f f f f f f f f f f

: : : : : : a. s.s s. s. s. s s i l i aaasmara s.

rrrrrrrrrrrrrrr

sssssssssssssssrsrrr Ee: ate xtaaaaaaaaaaa!&E=x~*cassa-

~$Bl.eess Ra=-- rrrrrrrrrrrrrrriffffffff@ fiffffs f g- -~ ~~s"s_it.~. -~== '8 ~ ~ e ss g ~~g: 8 .,,gg_m, 3 -~ gg:s:s.E== 55..: =-~II=_:1 1.I za-la::[ss ,3,,e E r .~_ m.. rr .g te.gg. [r ris serrum a errrrellis -rfas5s:s: g .E=e aIEEI

rre E.R~E.E.dr

. E. E. E. E. m m m m m m m R. R. R. R. R R. R R. R. R. R. R. R. R. R. R. R. R. R. R. R. R. R. I r i ~~ EEEEEEEEEEEEEEEBBEBEBBBBEEEEEEEEB88 kEEEEEkEEkkEEE*NkkNkkkkkEEENkkkhkk sssansassarrrrsssssarzersas:s:sasss $$$$$$$$5 $$$$$$h $h$$$$$$$5b$$$$k D-4 f

1 i l l l i V t s-ssss I .:: : 2 2::..:.Ed.8sg2232222EBE*2Ek2. ~~~sss sss ss s sss s sss-sss-888: :';$F: 28$8888888$$$$$$$8: : : : : 8$ l [ -n e f ses 3 3_ 3_ g. i E ;s r S E O 2 YYY-~~~~-~~~n -- --~~~~~~n -~~~~~~~ --eeeeeeeeeeeeeeeeeeeeeeeeeeeze v E figassesssssssssssssssssssssasis e E f E 3 3 3_ 3_ 3_ 3 3_ 3_ 3_ 3_ 3_ 3 3 3_ 3_ 3 3 3_ 3_ 3_ 3_ 3_ 3 3_ 3_ 3 3_ 3_ 3

r Eiiar.a++k+EEifIIE+EEsI++BEIv.E88888I+EI+BB

+ + + + + <. + + + grsentB8 E

ccRRE=s=s=s=a=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s=s

1 1 E_ E_ E_.t.:, s.t

.:.. t.t, r, s.:.. s.s.i., ..t _3 r s s. ~ ~ ~ s. s. s. s. s. s. s. s. s. s. s. s. s. s. s. s. ;. x. r. u. s. s. ;. s ; ; : : s

--:::rer:rrrrrrrrrrrrrre:rcr:rrrrr i---

.grgsg.__________________________._ ,;gggggggggggggggggggggggggggg t w -... s s s s s s_ s s s_ s s s_ _s _s s s_ s s_ s s_ s s s _; s s_ s_ r s_ ux s" $_ _$.*.*.d._f _f f f _f f _f _f _f _f _f f _f _f _f f f f k f _i _t _i _f _f _f f _f _f s2=rstene sErsatsasse~ Es3cc:::gggggagasases ss g1sss1yss fif9??tiki 22myyyTi?II titsystEE:EE - ~ ~ . ~ .s er ..s. ~ ~ a r = =-s

2

~: ~

rr:;-~g,,p p

~- ~-:: ~1

..*:il,ss es

~~ ~~l !rr*_ggs...-~~_5 gg! sgf !!! lf.g:E5eg((:c..a.gg':r:sg ww- ..s EsE 55r... EER:_g IEs!.s.ifusss sa aa z~$$nnn:::::::::::::::::EEEEEEEEEEEEE ~ R ssSEEEEEEEEEEEEsEEE mEE:::eeeeeeecezzeeeeeeeeeeeeeeeeze asssssekssssssssssssssssssssssssssa 33333333333333333333333333333333333 $bb bbS$kk$ Y b b$h$hhh$ gE b D5

522222:2222RG222222: 228;:. % % % % % % % % %

EE.EE: : 8 8888888G8GGGG888888;GGG GG;GG;;G

~~-------------~~~-------------

RRRRRRRRRRR$2RRR$RR@@RRRRRRRRR$$$$$ EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE 33333333333333333333333333333333333 v + + < v weeeeee eeee++++ e we weeem EBEEBBEEEEEEEEBBBBBEIEEEEew

EBIEEEEBII l

55555555555555555555555555555555555 l z,zxxxs::xtx1:>>>>>>>>>>>>>>>t: txz::xzus:sts: t:zzta l w w =w............=. w w w w w ww ww w w w w w w w w w w w w w w w w w ww w w ..Eiii5iiiii3i1555iKiE5KlE5KK5E5KKZEE

: r

rtrrrrrrrrrrrrrrrrrrrrrrrrrrrr

_-_-----------w

- - - - - - - - - - - w - 11111111111111111111111111111111111 EEEEE

..EEEE EEEEEEEEEEEEEEEEEEEEEEEEE 9Eiikff95ii99iifff9999iifff6

i99995E l

3rEER~%R4%RR 3RRS07373~??fG$3S573$2 33333333333 ~~~~~~~~~~~~3333*333*333333*2~33333*3 ~~2~~~2~~~~~ 2 Rs ~ aasasa a a a a a s a s a a s a a a a a a a a ~s a a a ~a ~a ~a ~a a a . ~ 99 ~ Es =~2-* EE ~ a= See-s i t 5".~ pp + : : w3

=9 gr-r 55: Ew=aa-*" gees 58w w: : *

~BRE f s"!! .3 As 8 s s : : E g p : :r r ! : r s = I I "E g x v= j... E * ' s a s 5 B E . g : :a s. zz2Ettr:: B

rEEll888.rrrEftessEss!!s w

mesammenmessemesmememommoesmesmo...se. RRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRRR EsEEEEEEsEEEEEsEEsEEsEsEssEEEsEEssi 33333333333333333333333333333333333 ?' d f.f :& J d J J J i d i s f d A d a f i d f f j d 4 J j j f. Ci tdfdd E. 2222.22... D-6

1 I i 1 l I i 2RR2

- - 22: 222 2: : 22 222 2e R2 2 :2 8 8sg g *Ec Eq s CER%

% % % % % % % % % % % % % % % % Es% % % % % % % % GGG$$;GGG$$;;GG88886C$$$$$$$$$$8858 i i 8888E88888888GG i iii"Tiiiiii"Ti St&&tSt&&&&&SSS 333333333333333

g..p5k!kkkkgkgg w---

ak a a aa

===

~~~~~------

R. R R. R. R. R. R. R. R. R. R. R. R. R. R. R. R. - - g g g g e g g g # I I I I Iggggggg IIIIIII g masssssssssssssssssa 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3. E' E' B' f. 9 9 9 9 9 9 9 9 9 9 9 9 8 9 X $$$++8888$II$$$$e$ 3$$$$$$$$$$$$$$$1 + + + 3 8 B

~~:::

55555535555555555** E~~~a~a~a~a~'~a~a~a~aa*~*~* 58 srssar:sarrrrrrr: >>>>>>>>>>>>>>>>>EEWWEW 5555555W55WW ggg1gg1>ggggg5>ggg g g IIIIII!!!!!!!IIIIffgooooooooom i rccc:rcccccercrec--_ _ _. - - - - - - - - - - i t t. =. = = =. =. =. =. =. =. =. =. =. =. =. = 4 f_lallilliiallillEEEEEEEEEEEEEEEEEE i E_ E_ E_ E_ E E_ E E E_ E_ E_ E_ E_ E_ E_ E_ E_ E E E g g g g g g g g g g g g g g g _f _f _f _fr _i _f _f _f _f _f _f _f f _f _f _f _f _ _<. _, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ S E. 2 0. t. C. E. R. s.1. G. i. t. E. R. &. G 2 2 E * '3 3

2 0 A
2 R *t $$$

suu2 3eceeee tittttttttttttttttttCCCCCCCf.CCC CCC zaaaasasaaaaaaaassaaaaaazaaaaaaaza .= -~ . ~ x2 --s

== 5 ff'*ii==g.~bw~w dd I!=g n

E***

3r==="tig5===I r 31**** 30 = l R RE R E s ! g f f =s t s s s i.. [ [ - - f l a '*I =. ~ -. -5::::l_ ~ -* >= ..wsrgg-siltia!.:::Exa.I.115W ~ 3 s r

==============cggeeeeeeeeeeeeeeg E.EEEEEEEE.E.EE..I..EE.E.E.EE.EEE..

4 RRRkkRRkkRkkRRRRR&&&eeeee?eee*egese assassassamassasst$sSE$SESESS$$th$$ 33333333333333333333333333333333333 .d4ididisi.'d4JJJudifafdCCCCCCCCCC 22gt=idididi4Jf i

===22222. 2:22:322: D-7

s Es. - N s sss ss s s ssss sss sss sss ss ss s ss s ss 88888888888888888888888888888888888 i TTiririTrriviirTTTTTTiritiTriTTTTT SttttttttttttttBERSttttttttttttttBS 3 3 3 3. s. s. s. 3 3 5 s. s. s. s. s. s s. s. 3 3 s s. s. s. 3 5. s.s s s. s. s s s s W W W W W W W W W WW W W W MW fW W W W W W W W W W W W W ...l555 W $$WEW. l W W.W E W W W W W W W W = =.= W W. W WWW - - IUUIN UINUUU$UUIUUUI5U NYI UIU NI ag a $ <$. $ *a 5. $ s s. <g a *m e E g.geenoe$agasggeeegg$$.$ 357.S

esxe. x :.
s, s.

g . v. s 999999I.ii.9I9999999999999.ii.i9.i99i999 3 E E E E 3 E eeeeeeee e e e m m e w e e e e e e m w e e v. w e v. e e v. *

e 555$$$$$$5$$$$$

$$$$$$$$$$$$$$$$$$5 ooooooooooooooooooooooooooooooooooo EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE E t a z z a t t t t t t t t t t> u t t t t t t z i t t 3 5 2 E t a t t oooL ooooooooooooooooooooooC oooooooo U"UUUUUUNUNNYYNNNUUUUUUUUUNYUUUNNNY

a*

EEWbEEEEEEEEWbbEEEEEWbbE..WbbBBBbEWbEEWBEEE W W W W W EEEE8888258 EBBEBE5888BB881tt?*EEEB5 EEEEEEEREEEFiffffffffEEEEifftEEEFFF

$$~$?*t 3$28

~~ ** '$ tR:ncUcen c c 2 c< c< e< t 2 c r e ' - ~ ~ $s 3 ~ 2: G t.Rt ccffflelle eccc 9 s s . r: c c r. ( c c

asssa asaarasaur.ssaxxzumaxx asusa aa a

. N Nm h$ [. 55 pp o ~. s55"~mE 5 e 5E - ~a 3 . ~ o . e y gy ~yyyW W -~ W W .g I**gg*CO-:".t R R N I -NE U IU W W O oO W !=="!! IW 578*t333E"" { e**arW U:.ssIzeIgg:ia:rras:::irr s

asstal:tts:gs m

r EE W nn

: : : rrrrr S.e e.c e $ s $ e e s e e $ e.e e.e $ e.s.e e $ e s e e e e e e e $ e.

S S S S S S S S S S S S S S S S SS S S S S S S E S S E S S E E S S S $$e$$$$$$$$$$$$$$$$$$e$$$$ EhbbhhEbhhhhhhhhhhhhhhhbNEEbbhhbhhh 333333333333333333333333333s3333333 ... - - - - - - - - - - - - - - - - - - - - - n P. ~ a. k^ ~ h ~ D-8

22222::::2Itt?22~ssesEt:s s22:2222EEs ss s sssssss ss sssss ss s ssss ss s s s $$ttttttGGGGCttsstG8GCtGttsst3GGGGG GGGGGGGGGGGGGGGGGGGGGGGGGGGGGGGGGGG iTiriiTTTirTTTiririritiiiiriri TTTT &tt88888888888888888888888888888tts $333sWs3333333333333333333333s3ssss -{ - g g g I V E g g W: W [ I r W W W W g W: W: W W y V W [ [ g g [ WWW y rrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrrry $5SSIIIIE5555EEEEEEEE.EEEEEEEEE$IIII 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9. k W 9 9 9. 9 9 9 9 t.swi. tit.IIt tistittttttttttttttititttttt2ttttti ...,v............-a..v.... err

rrrrrrrrrrrrer=rrrrrrrrrrr=

conoconococcocomanocomoooooococonom 55555555555555555555555555555555555 >>,,,~ .r,-- 1 it 2222**2222222*2222**2*22222*2222222 EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE Bess 888888E88885E8B888558E8285E5E8B fiffitfEEEktifEffiiEEEfffiiiiiiiifE i C l R. E. N. y $. & $. H e" ' "e* l f r "e E ~2 0 0 3 C $ 2 " P

2 ~ A "e B ~ B 9~

d ~~~~~ee e ~ ~ ~ o C CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC aasassas: s aasasuaaasa: asrars: aasa - ~ -*= -~.sg.~- - ~- - ~ rsg ~-

ss

-~ ltyg- -WWe===v r --~-~ !!-~ z.::gss srs- ::n-~III:s:=r -~ --EEE::...-g-e:t:

I s

ss .ss :.szer::IEE. EE f l e s s s f e r r :. neereII: s.res-- rur 5: -r

????????D???*??*8???9999&&S&B?????

EEEEEEEEEEEE"EEEE.EEEE.EEEE~EEEE.EE B222???????E9??B**?????????????2*?? hbhkhEhhhhhhbh khhhhhbbh SEhbbhhhhh 3333333333333333333 33333333333333, 4 EE~EELEE%~fadd2fddado*Jddasjdfiaadddi JdJdddddi %%%%~%%%%O00CRO~0~04%A444 D9 n

Gt 89-10 8110 voGilt 1 m 75713 ** item ort eattD vat VE D if 51 tug a4D SUrvt tt taWCt (Gt 8010) 95/06 GL 89-10 8110 voGitt ? M75 754 emitw ort satto wat,tp ttsfluG aun sinvitttanti (Gt 89-10) 95/06 Ct 39-1t5 8110 uniterorD 3 '475 7 % moton nrt eatt o val vt p tt S11mG aan Stevt a t tawCI (GL 89 10) 94/12 a Gt-89-10 8110 uur 7 m 757m untew wt eattD vat Vf D 1t 5114G aND 5tmvt IttauCt (Gt 8910) 95/06 GI 89 10 st110 uot t tette m75 7 W mntra ort satte vaivte it Siles aun 5'myt ittawCE (Gt 89-10) 94/12 'f. t,t-89-10 8110 7 ton 1 M 75 741 Petite ort satto ValvtD itstimG aun Simvt IttawCt (GL 89-10) %/09 f.t-89-10 8610 llou ? M 75 7.? mntf* ftteattD vatvtD If5ttwG awn suevtittawCt (Ct 89-10) 96/09 't. (4 89-16 8117

- tatn 8011tyt 3 M74P77 lustattat tau Of NaeDr wt D ut iut t t vt 47 (Gt 89-16) 94/17 Gt-91-13 8119 SealDunrD 1 mP t tr 7 15st4ttat steytti Watte systra f alttfel5 (Gst 134) 94/11

) 85. Gt-91 13 8119 StalDuctO 2 m81168 f 5st 41 t al steytti Watte Sv51tm f attists (G5t 130) 94/11 l ." 6 (A 97-01 8170 Catautta 1 mal 4.P platite vtS544 51sts ispat twitGo t ty (GL 92 01) 94/1? I 757 GL - ?? 01 8120 Catausa 2 M834 a.9 electoe vt S5f t steta ttpat luttGetty (Gt 92 01) 94/12 258. Gt-92-01 8120 teorte stallow M83455 et attoa vt Stit strut ittat intrGetty (ta 9? 01) 94/17 259 Gt-97-01 8120 Davls stS5s m8373? et ation visSt L sletrllmat 34ttGettv (Gt 92 01) 94/17 260. (A 97 01 8170 DetSDtm ? M83458 etattoe vt S5t t stetratsat InittAliv (Ga 92-01) 94/17 h 261. Gt-01 8120 Det$0tw 3 M83459 etarton vt5stt stetxitmat i n ti t.e l t y (Gt 92 - 01) 94/17 2 262. 64-97 01 8170 taetti i me3461 etation vtsstt strutitmas luf t tA t t y (ta 92- 01) 94/17 O

763, gl.,7 OS 8170 taattv 7 m8346; es at toe vt S5t t 51eur itmat smittAttv (Gt 97-01) 94/17 264 Gt-92-01 8170 GleMea 483713 etstvan ve ssit Statu tt$at lW!tGRitt (Gt 92-01) 95/09 165.

Lt-92-01 8120 taSattt 1

P 34 75 st ation vis5tt Steuttimat smit tat ti (Gt 97-01) 95/07 766.

f.t 92 01 8t?O tasattt ? ME34 76 erstite vt5sti stetKilmse futit#117 (GL 97 01) 95/07 767. Gt 92-01 8170 t!MRIta 1 m834 77 et ation vissts steixtonal Imit tA ll t (Gt 9? 01) 94/10 268. G4 - 92 ' ' 120 tiMtette ? M8 34 78 et actor vt 55f t sletM ttpal le f t (A l ti (tA 97 01) 94/10 269. Gt-9?-On 120 mittstout ? me3453 etarton visset $ s etsr tun at quittAtty (Gt 97 01) 94/12 770. 64 9? 01 81?O PitGetM 1 me34ce star toe VI55tt stetM ttmat gutt tat ti (Gt 97 01) 94/17 771 Et 97 01 8170 Qua0 Citit$ 1 MP3V1 etattoe viistl $1!tM it#at tuttGetty (Gt 97 01) -/. ???. 64-97-01 $170 Oua0 Clitt ? ? MP 350; et ar ttw vi s5f t St atsrittat twitGotty (GI 9? 01) /- 273. GI-97 01 8120 Supeer t 1 me 3'17 et artre visitt siete ttent luf t tAITY (Gt 9? 01) 94/17 [ 7 74 GI 97 01 f.170 SU53KMawasa 1 mfit ir st attoe viisit 51st4 turat 14tt tAlti (Gt 97-01) 94/17 2 75. Gt 92-01 8120 SU50utnauwa 2 mE3519 et attoR visstt Stetar tuent INit tat ti (GI 92 P1) 96/12 ? ?6. Gt 92-04 8171 Coorte Stat tog mM4? B mue t i vt t twstevue stat tog (Gt 91-04) 95/01 277. G4 97 04 8171 matts 1 m84?n? But ti vt t testnumeuratton (Gt 92-04) 94/12 7 78. GL 97-04 8171 LaSattt 1 M84785 Bue ttvrt lastevMtulattou (Gt 92-04) '/- 779. GL-92 04 5121 LA$attE F M84286 Itue ttvtt IN519testulat tom (Gt-92-04) --/- 780 GL-97 08 1708 Stavte valttv 2 M85517 Intemo-tag (Gtutett Ltitta 92 08) 96/03

l l 4 m e n m e m m m m m m m m m u m e n. m m m m m m m.~ -mmmmmmmm oooooooooooooo-oo ooooooooooooooooo s ss ss s sss s ss s ss sss sss s sss ss s s s s s s s s o ~4~~444~~~444~4~4444444444444444444 eeep oeeeeeeeneeememeneeeeep eeeeeeme ..................k 5 5 5 5 5 5. 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 $ $.5 5 5 5..".5 5 5 $. $.$ d w w M. M. M M t M. M. E M.M M M. M M. M M t M M. M M M M.t.M E. M.5 5.M M. M M M M III IIIIIIIIIIIIIIIIIINE.IIIIIYIIII 33333333333333333333333333333333333 .$.$.O.Y Y. .O .O O $ Y Y Y Y .Y .$.O.$ Y $ O .Y .O .O .Y Y Y O O Y S Y Y - - w ---w w -- w w w - w w w w - - - w - w w w w w w - w w - - - 6L. f.f.f.f.f f.f.f e f.f L.f.f.f.f.f.f f.f.f.f.f.f.f.f f.f f .E f f.f f. L. 5 .E.E.E.1 1.E.1 1.E.&.E.E.E.E.E.E.F.E.E.1 1.E E.1.W.W I.I I.I.I.I.I.I.I ~ b < < < < < < < < < < < < < < < < < < < a. e < < < < < < < < < s. e < < < x ffusttaFAattsEtFarYrfristar 1 : aura m -~ N g" N r-E. ~3[5. = nae .55 .5 = . ~ i gg =* g-~SS-5... - ~ W"*wwA.**$~5g" !gI*w EM-~2 55 we..r.EE.g. ~._!:: 55 I* a n o a E E E M S. 2 2 2.g,.. E E 2 2 3 3 3 " 55 . g - 1..g a;53ww[e rr3a= r .m w - -w CrYEEEE E 8 E E E ~8 8 E E ~8 [ ~8 8 8 [

t [.8 ~8 8 8 8. 8. ~8 8 8 E.8, ~8
8 E ~8 8

~ ~ ~ ~ e e~ ~~ ~ ~ ~

w

-w 88888888888888888888888888888888888 44444444444444444444444444444444444

o. p p o. p e. m. e. > > > e. > > >.. e. e. m. e. n. e. > > e. o. p p e e. m. e. e. e. p 33333333333333333333333333333333333

~~~~~~~~~kRRRRkkR kmmmmmmmmm o mmmmmme D-11 n

i l 1 Estasassassenesssanssss E22tEEaE e ese s~~ s~~~~ ~~~~~~~~ scestces testessettesssetests*** ~~ s ggggggggggggggggggggggggggggggggggs ssssss&ssss&ssssssssssssss&ssssssss

=======================

=. = = = = = = = = = = = = = = = = =.= = = =.= = = = =.= =. = = r. e u x N55NNNN555555555555555555555N33NNNN assassaaaaaaaaaaaaaaaaassaaaaaaassa t t.t.t t.t t.t t t t t t. t t t t s s.t i t t t.t t t i t t t t t t a ttttttttttttttttttttttttttttttttttt !!!!rrr!!!!!!!!!!!!!!!!!!!rrstrrr!! cae.3-,c,~55g, ~ I lifiltil,s,i

l. l 3m.cy~

e<<5757775.~ ++ vfststnittists t ~ .,nEs ,n,r. m.. =,llE-Iff.m...in = =,,,~ -~.. ll_=,.. r-,. 33 m re-s- st:---- IlliffffEEgee.gg en!.-~vi.. g ~-. s.rffisallasIllEE!!!Nffill, = te....-

==.~. n.a.t.a.n.t.a.m.i.n.s.t.a.m.a. NEE.E.E.E.E.E.E.E.E.E.E.E.E.E.E.E.E.E. 35555558BFE88885EEEEEEEEEEEEkEEE888 s$$skRsR99$st$$$$ss$ssss&&ss&s$s$$$ 53333333333333333333333333333333333 f f i f i.*d d J e'd *i s'f f f f j f j f f f i.*d A J J f ~~d e'f ammm2222222222 mmmmmmmmmeAAAAAXmAAAm D-12 A

351. 64 92-06 1206 licus 2 m85627 t ut omo t ac (Gt at e t r t t tit e 92 08 ) 96/03 352. GI-93 06 (304 St avt e val t t v 1 mN.8 3

etc toutetg Sv51tm taitter & WitMtreawat of etta's (Gt 93 04) 95/10 353.

Os-93-04 1304 stavte vattti 2

eNA 52 ete toesteoi Svst19e valitet & witweawat og etta'5 (Gt 93 04) 95/10 354 ct-93 06 1304 seat 0wono 1 mNc 53 ore toutect Sv5tta sanitet & vitMNtawat of etta'5 (Lt 93-06) 94/11 355.

Lt 93-06 1 306 BeatDwtxD 2 mNA 34 ese touteot Svstim s att ter & wif eenwat of etta's (Gt 93-04) 94/11 356. 64-93 06 1304 aveau 1 mNA35 sie touteot svi*t se f att utt & wi tweawat or atta's t G4 93-05) 95/10 35 7. Lt-93 06 1304 Sveou 2 MNek em toulsot Sv5f t m f alt t*r & Wit @eawat of etta'5 (Gt 93-04) 95/10 358. Lt 93 06 (306 (Attawar 1 MNA37 ete (tmtect sistree sattles & wiimenwat of etta's (Gt 93-06) - /- 359. G4 93 06 L304 Catawpa t mNAle ett toutst.e tuttles salttet & wt teceawat os etta's (Gt 93 04) 94/10 360. 6t-93-06 1304 Catausa 2 MNa39 ete touteot Sv5ttu f attler & witenawat ce e t t a

5 ( Gt 93-04 )

94/10 361. 60 93 06 (306 toMautMt stae 1 =NA60 ete touteot 5751tm e alttet & wt teenwat os etta's (Gt 93-04) 95/10 362. 64 93 04 L306 Comautut Ptse 2 MN461 are tomisoi Sv51tm s attutt & witMoeawat os atta*5 (Gt 93-06) 95/10 363. L4-93-04 1304 0 t tout 1 MNe42 erv) touteot 5vstim f atttet & witMonauat og etta's (Gt 93-04) 94/12 l 3en. 61-93 06 L306 D C toot 2 mm6A3 ete touteot Sv51tm sattver & we tMoeawat er ett*'s (Gt 93 04) 94/10 l 365. 64 93-06 1306 clasto tauvon 1 MNe46 ete touteot Sv5ttu salttet & witnDeawat or atta's (Gt 93 06) 95/10 366. Lt-93 06 L304 Osasto Canton 2 MNe45 ete touteot sesttm satttet & witmoeawat os #Cta'5 (GL 93 04) 95/10 o 367 Ot-93 06 t306 taatti 1 mN466 em touteot sv5tta salttat & wt tenawat of etta's (Gt 93 04) -/- U 368. 64 93 06 (106 taetti ? MNA47 etc toutect 575ftm falttst & witM0anwat 08 otta*5 (Gt 93-06) -/- 369. LL-93 04 (304 GIBMan W A48 em touflet Sv5f tm f atttst & witMDeswat of etta*5 (Gt 93 04) 95/01 370. Et 93 06 1304 wasels 1 MNA 7 etc toesteot Sv5tta f atttst & witMosawat of etta's (GL 93-04) 95/10 371 GL-93-06 (106 luotas rotut 2 mNA50 ste touteot sv5tta f alttes & witnosawat es atta's (Ct 93-06) 95/10 372. 68 93 04 1304 luolas potut 3 MNes t em toutsot Svittu saettet & wiimenwat Os etta'5 (Ct 93-06) 95/10 373. 64-93-04 t306 etwavut t m&c52 etc touteot sv5ttu saettet & witnDeawat of etta*5 (Gt 93-04) 95/10 3 374 6t-93 04 1306 utGulet 1 MN#53 p(c touteot Svittse f aittet & wt tweawat os atta's (Gt 93 04) 95/05 375. GI-93 04 4 306 mtcuter 2 =Na54 etc toutsoi systres satttet k witannawat tm etta's (Gt 93 04) 95/05 376. 6t-93 06 (304 8 tit tstout 3 MN455 tee tosisoi Svittee s attler 4 wa teaawal or atta'5 (Ct 93-04) 95/11 377. Lt 93 De L304 mortu auun 1 MN45e ete touttot 515 ti m ' a g t t*f & wi t @eawal of itta'5 (64 93 04) 95/10 378. Lt-93 06 1306 uttin auwa 2 mH457 tre toutstg svstise s alttet A wit +eewal os etta*5 (Gt 93-04) 95/10 379. 61-93-06 4304 tolut 9tatu 1 =N4W ete tosivsti Sv5f ta f attter & wit @eawat ce etta's (Gt 93-06) 95/1(a 180. ct 93 06 (306 Potut statn 2 h&a59 em toesteot Svittu eattunt k wituteswat es stta's (68 93 04) 95/10 3P1 f.t 93 04 L304 Peatett 154 nun 1

- N.8An s'e (fMfoot Sv5f tm salttart & wt tueeswat os atta*5 (Gt 93 04) 95/10 382.

Gt 93-04 (306 Pealett 35tano 2 MNe61 em touterit 575f tm f alltet & witHDeawat of atta's (Gt 93 06) 95/10 383. C.t 93-04 L304 e0Beu50se 2 m36862 etD touteot Sv5tf 84 f atttet & wtIMDenwal os atta's (Gt 93 04) 95/06 184 Gt-93 04 L304 sattm 1 M86863 ete toutent Sv$tta f attUet & witMDeauet Of etCa's (GL 93-04) 95/10 385. Gt-93-04 L304 Salta 2 MN464 ete touteot Sv5tta falttmf & witMDeawat of atta's (GL 93-04) 95/10 t s

3%. Lt 93-04 1304 st aseOrvt 1 MN#65 etc tretent svtttm talttet t utt@eauai 0 etta's (Gt 93-04) 94/10

387, t.t-93 04 L304 stovovan 1 M*/J W evo trateot sisit M t alt tel & Wi tnoenuai os arta's (GI 93 04) 95/1C 3M.

GI 93-04 (304 stoUovaN 2 MN#67 em rosetect sys tt M t a t t urt & Wi tureawat os atta's (Gt 93 06) 95/10 389 u 9306 1304 50utw ituas 1

Nasm ero towieot sis tt M raittet a wif eenwat os arta's (Gt 93 04) 95/10 390.

04-93 06 L304 graf tw te mat 2 MN#69 em tretetw sv'st m t a titet 4 vivevavat os atta's (Gt 93-04) 95/10 391 st 93-06 L304 stseer e 1 MN# 70 sto (twtect sesttM sattter & we teenwat or atta*5 (Gt 93 04) 94/12 392. M -93 06 1304 5U881 1 MMe# 71

(st ton t ect 5tsttM taltver & WIteceawal os atta's (Gt 93 04) 94/10 393.

Gt-93-06 t304 stroy ? MNE 72 ere touteot systree s attter & witwornwat et i.tra's (Gt 93 04) 94/12 396 La-93-06 L306 ttett y rotest 3 Mar t3 em toestent sv' Tim s a t t tes & ui t ure awat es atta's ;Gt 93 0A3 95/10 39'. 64-93 04 t it** ttparv potut 6 MN P 76 em Comtect %vstt M satttet & Witoccavat of att a 's (Gt 93 04 ) 95/10 396. 6t 93 06 1304 v0Gitt 1 MN.P 75 em t ou t p0t sisit M taittat a wat e eswat of etta's (Gt 93-06) 94/12 391 01-93 06 1304 v0 Gilt ? MRA876 ero toutpot sv5 tt M ralttet 4 wti etawat es atta's (Gt 93 041 94/12 398. 61 93-04 1306 W0tt tette MN# 7m em tiettet sv5 tt M saitUse & witweesuai n etta's (Gt 93 04) 95/10 399 64 93 Os t306 rios 1 seM6P80 ere touteos systtM talttmt i un tepaust of etta*5 (Gt 93 04) 95/10 400. 01 93 04 L304 Flom 2 MN#81 em Cou180t systfM talttet & wt1Neenwat es etta's (Gt 93 04) 95/10 401 Gt-94 03 5125 89tmsu1CR 1 M'M1084 toet specto teart tug -/-- 402. 04-9' 01 8125 Betertutto 2 se90085 tt*t 5weate toattI#G -/ -

403, t,t-96 03 5125 Cttul04 1 M90086 ttst swe0tc teattlNG

--/- 606 61-94 03 8125 totT1e 51all04 M90087 Ctet Sp*0te teattless --/ - 605. GL-96 03 5125 Dets0 tis 2 M900PA Coet $ Hecto teattlWG 94/12 406. GL-94 03 9125 DetsOtN 3 M90089 EtSt SHttRJD teattlNG 96/12 607. 61 96 03 5125 cuant seisot0 M90090 tant smerte teattluG /- 606. 68 96 03 8125 f tMel 2 M90091 (cst SM*0UD CenttING -/-- 609 68 96-03 9125 tiI2PateI(t M90092 005t se*0tc teaEtIwG 96/12 610. 64-96-03 3125 Gen 4D GUti 1 M90093 (t*t SM*0lO CostelwG - /- =11. 01 94-03 SIM teatta 1 M90096 trot Specto teattlwG 96/12 612. 08-96 03 3125 nattu 2 M90095 ttse suerte teartius - /- &l), tot 96 03 8125 IsOpi C9tte 1 8Cito06 It*t SM5ftm teatFtWG -/- 6 14 Et-96 03 8125 tasatti 1 M90097 ft*t 5840VO teafRIuG +/- 6 15. 64 96 03 8125 tasatts ? M90090 Cott 5 *00D teattlesG /- 611. 04 96 03 915 *Listrltil 1 M9n099 CC*t $N t*atelleG - /- 617. Gt-96 03 stM tesepttu ? M90100 tant sumous teartissG "/" 418. Gt-96-03 etM mattst1pm I scoo266 toet sisscue tentatoG 96/10 419. GL-96 93 31 5 toestIGtt9 ss90101 test sancup teatuttsG -/- 429. Gt-96-93 91 5 BfE tettE P9tet 1 9s90t92 test ' sects tentatuG 95/96

E2.

2..:3.222:22.: 8"6.

322.. sss ssssssRs ss ssssssssss s sss $3;;;$: : $: : 38:592883: : 38$'**$$: : : : : sss s s s s 8888 Tiii SERE.. 3333BB gg 5555ft

2. : 2 2 2. E.

/- comu..

====-- ..rr E.E.E.E..E.E--------.,<<<<<- gggg,3 s .h,* b,b I I 6*Eu 5,, as g"Efff.. .E.BBBB m.a.a. +.t R. R. R. R. R. R. R. R. R. R. R. R. R. R. R.

EEEEEEEEEEEEEEE o ----**ssssssssss ecocory---------

sssss Gitiittittitit----

-)gggBB;w;v..a.ma.;;;;;;;;;;;;;

s v...++meem e-::

eggggg5grrrrrrrrrrrrrrr rrrrrrrrrrrrr strrrrrrrrrrit

.i.t.t.i.t.t.g e e e e f I ~ B i t t -

g ! ! ! ! ! ! ! ! ! ! ! ! ! !

$aaposessas eeeee .t.t.t.t..t.t o 'r:::::::::::: _______.----~~............... sae.sasas.ss.s.s.s.! a tt -.e r r e : : : : r r r r e r t es Essrasse:~ scCeeeg~astssargsres?9Rg - ~ - ?2ccacaccacas ag==us fiffffffffffamaturtrrrrrrrrrrrrrrer ~ .~ E-~- ~~ ~ ..s .~ er eess E-r 2 ~: ~,

== sist r -~ 88e. se 5 =-ss.

s a.

Mrfguerat:--!!.:it ee ~1 8I~s~-.~.:.als--W =e...--- a= r rr: Bee.r l Eff: 55 .22353EIIEE.88sI=EE5555

Errr:BB:

C C. C C..C C C C. C C C C.C M 2 2 2 2 2 2 2 9 E B.*

B.B W 9 2 S S.& B

.................o.. 8 8 8 8 8 8 8 8 8 8 8 8 8 3 2 2 2 3 2 2. 2.*.E t.B E..S.E B.E B. S E 2 8 g g g g g a 3 3. g 4. g 4 g ? ? ? ?. ?. ?. ?. ? ? ?. ?. ? ?. *. ?. ?. ?. ?. ?. ?. ?. ?. sssssssssssss2kikkikittttttkkiittt1 iiiiiiiii$did555ddi$$55555555555$55 D-15 x

: 388:8G2: 2283:

8:. : : : :

: : : 2: 22Its:

s sssss s s ss s ssssss s s s s s s sss sssssss

G.38G88

^ GGG;8GG;GGG8 8 .....-..-.4 e. 4 4 4 b III I k k I I I I I I

I I I I k
I k 5 b. 5 5. 5 5 5 5. W,bbbhw Mw 568 5aa#W$$MM5#$$5a5Mw mv e v + a s W

8EEEEssEE8EssssssEsEEdididsstE5E8EE 3333.3333333333333333333333333333333 Y $ $ $ Y & Wo V, & & & & d We & W. @ $ $ @ & We @ We de We O de W. W. Y @ @ w w w w w e e e w w w e e m e w w e w w e w w e e w e w e w w w w w w 5 B B 5 5 3 3 3 3 5 3 3 3 3 3 3 3 3 3 3 5 3 3 3 3 3 3 3 N E E E 2 N E 5 .$55$$$$$$$ $ 5 5 5 5 $ $.$.$.5 5. $.$ $........... 5 5.E.$.$ I.I.Y E.E =.=., 4 4 4 4 4 4 6 4 6 4, 4, 4, 4, 4 4 4 4 4 W 4 4 6 .. 34.= . G S. 6 6 = =

555 55555w $55555555555$$55555555 5 .F .M.k.k .M .M .m.M.R.h .M.E .A .a.m.k .M.M.E M M A h h & A h b k m h M M 5 m m m w m m - m m h -->m m E r r r r r r r r r r r r r r r r r r r r r r r !!! C r r r r r r r m& 4 W e A Y b W e A &e k f h W he es e e e a mmmmm me m O w e w e e e e e e m m m mm e m fffffffffffffffffffffffffffffffffff e ~

8*

EE 5 e w e w r : E. e mGG mY b 3 ~ -Y y gg - - ~ e ~ -ne F-b b N 3 h 3 I.-88 co w ~4 w. 3 11*5 - - -.w w= = s. tt*:5g.. -w W. E N w a W W --4 s W Ip B -gg w o 5. = := :. 292. $ W W "a wwowww .a.-E~ E** E W WW WW W WWWWWWW WW WWW WWW W WW. W W W W W W W W W W ENEN N E NNNNNNENNUNN NN NNNNUEYNN esemememememescommemmeneemmeneemme. WW W WWWW W WW WWW WW W W WW W W W W WWW W W W W W W W W W UNSNN ENEEE NNNUNNECNNUNU USN UNNNN . ? ? * ?. ? ?. ?.? * ?. *. ?. *. ? " * * * * * * * * * * * * * * * * ?. ?. ?. Atttttttttkhttkkkktitkkkkkkkkkikkk1 D-16 1

E5:..$$: :::: $$$: :: $: : : : : ssssssII-t sssssssssssssssssss, s sssss

g;;:ss: ::::sss:::3: : : : : : : : : : ::CC 3

$!iiiiiiililillillillilifisill!IIII nennnenennennenen................... ennenenenenenenene dissisissisassiassiassaisssssssssas 3s s 33333 33 3333 3 33333 3353 5 33 3 33 3s s..s s

r. e. r. e. r. e. r. e. r. r. e. r. r. r. r. r. r. r. r. r. r. r r. r r. r. r. r. r. r. r. r. e. r. e S

e .v.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r.r = = = = = = = = = = = = = =: =: =: =: : =: =: =: =: =: ! : = 1 1 : =: = 1 1 1 1 = ... _.. r. e. r. r.. r. e. r. =. =. =. =. =. =. =. =. =.. r. e. r. =. =.. r. =. =. =. =. _r r _r _r _r _r _r _r _r r r r r r_ r _r r _r _r _r _r r r r_ r_ _r r _r r _r r r _r.r r ~---*;11ssan$axxxal 311 13::: sass *ee sE~ sss:ss +- ecenc 11111: 1 3 11trttrrrrrrrrrrrrrrrrrrrtverrrrrrt -~ . ~ ss ~- -~t!-~. pp.s -~ .~ 5g ~- ~~EEr..;;-~~g.ggg rEs. iGEEEEs~ rr-~is e==.. g a n e = =.. E E E a r, r r r ,, g _ _ r; ;.., j. ~, g g a s $ $ . ss re-essvra.$$ li,, EEIwrII8885:===rrrrrr= aver r=55mmil EE = 88;I53 $ $ $ $. $ $.$ $ $.$ $.$.$ $ $.$ $. $ $.$ $ $.$ $ e $.$ $.$ $ $ $ $ $ $ E mB S eesesseemmeeO S SS S S 5 5 9 3 S eS eeB SS S ..;EEEEE; ~~.E.E'E~EEE.E~E~E;~EE~EE 44k446444444444444644444444ee44kkkk ikkkktitikikkkkkttttttttttkkkk19tti $N.iii.5idie+iiiiiiiiiiiisis:'Sidillll i i eeeeeee++eee++a <.< a.e < e e e e D-17

(_ l l l-l l l

: : : : : :::::.:::.222222RRs25522222: 22 sssssssssssssssss s s ss-ss ssssssss 888388$$8$$33388: 33 EEEEEEEEEEEE88888 00000000^O"O*0000 fifffffffffffffff

=====e:::::::::

E.E,i,ll!_Il_i_fi_lill,il Il 668.$.6E66E.6f'E.E.S.8 EEEEEEEEEEE*EEEEE 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 : : : : :o :o :c :c :c : ::::::: oooo ccoooooo mRsR,RRR2RR.5."hRx$_50_:5_:: N I I I 5,R E RRRRRRRRRRRRRRRRRREBEEEEEEEEEEEEEBB EsEsisisssEsEsssEEgg((gyygggg5((ggg !!!332232322222222,,,,,,,,,,, '*??? 5 E 5 5 5 5 5 E 5 5 5 5 5 5 5 5 5 5 * * * * * * * * '8 8 8 8 8 8 8 8 8 555s55555s555555s588888888 gg;;;;;;;;,;;;;;; 555.55.55~5.5555.5E~5N*22*22*S22**2 I .I.. 2*2 M 5 5 777gg 7sg_) g g 2 7 g _3gg,_

._3_

EEEEEEEEEEEEEEEEEE&GGEGGGGGEEEEGGGE ss!!x s 4**$****:- p A R=EREEe E R * ~ S *! *4 0 '! x$ E R E ' C 8 S 8 ? ? % $ $ ) 3 3. ' ~h ": 29 EffffffffffffffVEkVI;fkfNh f ffffffk .t -~ .m -~ .E. g ..., 3 "' d : r._m f.

~5 25.~E s

5_ 5_ I ~ m .~-- .~ {r8E".~g

O.~@@..

3:~*~* E"*55 55 ~~.~"{E : O r f $ $ 3 I 5 _g g a s 5 5 g f. e e = :g f a W ! o o-~.25581 ee-- l:E.:g* "..~ PE at t: O*. EE3. ys* .. s. .i.t.s 5 E

I N-

= $?*??EEE**?E******224hkkk22hk%k2442 ELE EEEEEEEemeEmamEEEEEEE~EEEEEEEEe 2

2 2 2 2 * $ 2 2 * ".*.*.2.T S
2. R. R R R.R R.R R R :: :: %. % % % R mae

......................meame .= ........................=.=.......... tkkkkkkkkkkkkkkkkkkkkkkkkkkkkkkkkkk + e + e e e e e o e e e e e e e e e e a, a. 6

5 $ $. i.. d i. d i i i i $

diiiiiiiiiiiiiiii5555 e$eea .e. eeeeee D-18 C

o.o = ~.o ~ - ~. ~. ~ ~ ~.~ ~. ~ ~ ~ ~ ~.~ ~. ~ ~ ~..

,.. ~ ~ ~ ~ ~ ~ ~ ~ ~

888888GGG888888G88&&8884888&&888888 ..... ~.~.~..~.~.~.... ..~.~.~.~.~. .888g8888888888888888888888888888888 N N M > M M M M M M M M M M M M M N M M N m M N N M M N N M N M M N w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w w e w + + e + e e v, e weeew e v. w w w w

e. e w v. w. + + ew E

E E E E E E E E E E E E E E E E E E E E E s E E E E E E E E E ..4 4 4 e. 4 4.e.e.e 4 4 .e.e.d.e.e.e.d.e 4 u .4.e.e.e.e.e 4 4 .e 4 4 4 >>>F w > > > > >>>>>>>>>w e m >>>>w = >== = = >>> M > > > >W > > > > >>> > > > > > > > > > > > > > > > > > > > > > W 151111111,1111,11,1111_1,1_1_11_111_1_1_115,l,l,l w

YY 1

w _w w w w w w .B.e.5 .e.c.e .B.6 6.o.ce.66665h.6 666666h;.6.o.S.5 _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E _E E _E _E _E _E _E _E _E _E

: : : : : : : : :::: ~

ooococcoococosooo:o:ocoooooooooooocoo

: : : : : : : : : : : : : ::::~.2....__

EEBEEEBBBl.+EEEEEEEEBEEEEEEEEEEEEBBB ++++v.+++++v

v. + +

v. a. a.

v. e

e. s. w +

s. .., + + +e + mew 6666666666$66666666666 EEEEBE6EE6666 ooooooooooooooooooooooooooooooooooy 8 8 8 E 8 8 F & R E R R 8 8 & F 8 8 8 8 8 $.8 8 8 8 & R R 8 8 F R 8 8 oooooooooC C C ooc oooooC C O e m e e n e m n e m e e e e n o e w e e n - e -C -0 0 =0 C ~O oooooo e ~ ~ ~ ~ ~ w w YYYYYYYYYYYYYYYYYYYYYYYYYYYYYYY 5YY

f. f f f. h h. hr. hh.h.hhh.h.h.hhhhh$.h.hhb$hbb$!.hhhk v s W v v

+v d v v s v v .n + + + v v v + v w. w- + + d v + .n + + E.EEEEE.EEEEE.EEE5EE.a EEa EEEEa A ~..,. Es.o.. g c. -,,. - 4 o eA m-g Ep buA & C oco-***e **

o.w.,.

. - ~ -, 4 % o p N ew r= N m eM mm A e e mmem m a w 4 4 4 4 4 4 4 w w a w 4 e e e e w e 4 w 4 eeerrererrrerre+w + rr r r rr r 4-r e+r K L F L E gC W A A E E E O pO A E A E A A L L & C E C O E E dE E s E E E E E E E E a E E & E E I 3 E E 3 E E E E o - tw > e N _E _E u n

= w oo-N
~ m e

N W = = w ~ M L 6 ++ w E w o e 4 w w w w w o w ~M. = w oW " N - w w E E O. p Q = _ _ E k N wk 4 _- E E

NM

. h = 4 4 w w w. E _ = . E N = w ~. > w w w = E w w w h > > - w _ w . w N ww _ e W E .. *

W E y

h G E R e b IN _E ** w w 9 _4 = = M e - E E w w . E E S S _ _- ~ w _E 55 ooo..J E w *

c o 5 w-w w

_E 4 4 - E 4. .. J E. _ E rte E E E 8 8 8.e w -4 4 .. s ~~~ ~ ~ ~ ~~~~~~ ~ ~ ~ ~ ~ ~ NN N ~~~....~N ., N ~ ~ ~~~ ~ h~ ~ N ts %~ ~ ~ ~ N r% ~ tw ~ N N NN N N N ~ tw ts t u es 's sw 9% 9% 9% rw tu

e. e.......

~~~~~~~~~~~~~~~~~~~~~N ~ ~ ~ ~ ~ ~ ~ ~~~~~~ N N.N.N N N NN.N N NN N NN NN ew N N N N N N N N N N ev N N N N N N e e w w e. e * * .... m e e.

e. e.

e. w w e e e

e. e. e. m. e.

m e e

m. e.

NNdNN4 N4 NkNkNkkk4 kNk4 e 4 e hk4 4 4 4 k4 hkk titttttttttttkkikkkkikkiktkkakkkkk1 f. k. &. Y. ..... + Y. h. k h D @ @ P A A % A ' A A A A E" W E O K A L L E E J O an en' f f frf e an en e e f an e en en en en r en an ef' an.*' en e en en D-19

22222-222: 222282332: 2228852: : ::22: ssssss sssssss s s s ss ssssss s s s sssss sss 8$$$38888888888G8828: 388GGG8' ': 8CG: 888888888888888 0 05 00:005:00:05 e+*+5551!!5!eeeee +eweee a !!!!I ak*-

2 2

2 ~ E

n eeeeeeeeeeeeeeeeece>

lE555555555555E--------------Eg5g5gghigghgg5g556g r: s ,. s x E

EEE**EEEEEEEEE dadadadaaddaddaadad 777777-777777777777E
- EtBESBSEE&tttttttSE:

o a E_ s_ s_ s_ s_ s_ s s s_ s s_ s_ s s s r_ r r_ r_ r_ r_ r_ r_ r_ r r_ r_ r_ r_ r r_ r r_ r, Esasssssssssssshetteththeretattttt: ,.++s.e.v.+v...++8888888888888888888N +++v. ssssssssssssssssees-essesesseseasse s

.---aaaaaaazaz=zzzazaaz-asassess$ss&sssiffffffffffffffffffg ooooooooooooooo e

aaaassaaaaasa5aesaa-C C C C C oCC OC OOC CO . : : : c : . : :. c c. c. :.- e : c e. gssegsssgsssss_ssgsg., _s,[,I fitr . ff III. _ e e. e. e.e e. e z. e. e..

e. e e. m s arrrrrrrrrrrrrrereerezzz mezzzazas 2:esus-~s-<mer-sea s

e n se-.2 ca****RRRRRRRdRk.EERRf E

~ fiffffffffffffftttttttttttttttt f f

f********

-~ -~ s ees -~ -~ -~- 11:s- -~ = s ~ e gEgrr = -~n EE-~sgec:s

-~

-~- s- ~ ~ a aa, c:==gs.;.;gs*s lfees.,g:- .ss-ax!!ss[- gggift:ssenzarsexamasaffg sti I

= = = = = = = = = = = = =s = =s =s =s = =s =s =s =s =s = =

sassassasssss s s ss s s %%R%%%%%%%%%%%%OMNONORERO0NOROCOON: httktittttkhttkkiktttttktititttttti gagg a a ida fs:ssssssss25aaai sa 5g aaaasais st e 2222S225 ese,fstst 0-20 l

2 2 2 2 2 2 2 $ $ ; "t s s: 5 ~~~~~~~~s-s 8888888GG8GG;* iiiiiiiiiiiisi ssssssFsssssss E. s. s. a. s. s. s. s. s. s. s. s. s. s. e e e a e s' rrrrrrrrrrrrry 27;~;EEEE;;EE~

- - E*******5**

ea v v

v. + + v. v. v. v. v. e a.

EEEEEEEEEEEEEE

1 E. v.E B. 5 a$. v.1 E. a.E E. a.5 B.

a. B

v. v. v v

a a a 00000000000000 EBBEEEEEEEEEEE ii?iitiiti?iti cererrrrrrrere 1111111111 0: 0 1EEEEEEEEEEEEE EEEEEEEEEEEEEE f~C3%EkRRfG8582 ~* ~~~ fiffffffffffff - ~ - ~ NeW ~mE a=E~5-~ ~.rt: gg8 9=2: = t*** 5.Y 33 97&II"S$(( 18 55 44444444444444 memeseaN S W W W W S k N ............s. Riktiktktittti ' a A j i j u g s i *.; A J G23.3.2.231333 D 21

I 1 t 1 I ? I 1 l t

NRC FORM 335 U.S. NUCLEAR REGULATORY COMM:SelON

1. REPORT NUMBER YCu itor, b^u N.v T nd M 'Num-saoi,saoa SIBUOGRAPHIC DATA SHEET b-*. Havl (see inetructions on the revers.)

NUREG-1435 SuEE ement 4

a. Tmf AND SUBTITLE Status of Safety Issues at Licensed Ibwer Plants

3. DATE REPOHT PUBUSHED MONTH l

YEAR RH Action Plan Requirements i Unresolved Safety Issues December 1994 Generic Safety Issues

4. FIN OR ORANT NUMBER Other Multiplant Action Isuses L AUTHOR (5)

6. TYPE OF REPORT Annual

7. PERIOD COVERED (inclusive Dates) 10/1/93 - 9/30/94

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (if NRC. provios Division. Office or Region. U.S. Nuclear Regulatory Commesseorn, and malli"O address; if contractor, provide name and mallin0 address.)

Director for Inspection and Support Programs Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission W:shington, DC 20555-0001 U le Regu a cry iss and ma a oss ) Same as above

10. SUFPLEMENTARY NOTES It. AB8 TRACT (200 words or less As part of ongoing U.S. Nuc) lear Regulatory Commission (NRC) efforts to ensure the quality and accountability o information, a program was established whereby an annual NUREG report would be published on the status of licensee imple-ment. tion and NRC verification of safety issues in major NRC requirements areas. His information was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safetyissues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). Supplement 1, published in December,1991, combined these volumes into a single report and provided updated information as of September 30,1991. Sup-plement 2, published in December,1992, provided updated information on TMI, USI, and GSI issues and included status of all Other Multiplant Actions (MPAs). Supplement 3, published in December,1993,provided updated information as of September 30,1993. His annual NUREG report provides updated information on TMI, US1, OSI and other MPAs as of September 30,1994.

De data contained in these NUREG reports are a product of the NRC's Safety Issues Management system (SIMs) data base, which is maintained by the Program Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional person-nel.his report is to provide a comprehensive description of the implementation and verification status of TMI Action Plan Re-quirements, USIs, GSIs and Other MPAs that have been resolved and involve implementation of an action oractions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NU-REG report is to serve as a follow-on to NUREG-0933, "A Prioritization of Generic Safety Issues," which tracks safety issues u until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees. p

12. KEY WORD 8/DESCRIPTOR8 (List words or phrases that will assist researchers in locating the report.)

13. AVAILABUTY STATEMENT Unlimited

14. SECURITY CLASSIFICATION Status of Safety Issues at Licensed Power Plants (This Page)

TMI Action Plan Requirem(Ps Unclassified Unresolved Safety Issues (This meport) Generic Safety Issues Other Multiplant Action Issues Unclassified is. NUMeeR O, PAae.

16. PRICE NRC FORM 336 (2-40)

Printed on recycled paper Federal Recycling Program

jllll l ttao mia sr 7 s s 6 at te G ere. o eO mw wN ma sT u uf o s M r o R a E t t P ais co er ps ,l 9 5 5 ~ V S 5 C

1 D

n T A C I L H Ue Cr ". et N i 3 l ? a ,9a ?' - Io r G COm [N C F o ,I

1 H

VcFS S?- VL U^ T?W NO I 1 S0 S0 0 I 0 0 M-3 5 M5 E SO5 S S EC0 S U T 2 E A Y I T NE T R S A S O C. U V BI TD R DA L P A EL N IC O R TU O I I FF NG T F UE G O Y R T N L RI A A H N E S EP LA CW U N _}}

ML20078J768

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

L. PROCEDURE

SUMMARY

SUMMARY

SUMMARY

SUMMARY

=

=

=

===

rrrrrrrrrrrrer=rrrrrrrrrrr=

=======================

=====e:::::::::

= = = = = = = = = = = = =s = =s =s =s = =s =s =s =s =s = =

Navigation menu

ML20078J768

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

L. PROCEDURE

SUMMARY

SUMMARY

SUMMARY

SUMMARY

=

=

=

===

rrrrrrrrrrrrer=rrrrrrrrrrr=

=======================

=====e:::::::::

= = = = = = = = = = = = =s = =s =s =s = =s =s =s =s =s = =

Navigation menu

Search