ML20086T209

Status of Safety Issues at Licensed Power Plants.Tmi Action Plan Requirements.Unresolved Safety Issues.Generic Safety Issues

ML20086T209
Person / Time
Issue date:	12/31/1991
From:	Office of Nuclear Reactor Regulation
To:
References
NUREG-1435, NUREG-1435-S01, NUREG-1435-S1, NUDOCS 9201060172
Download: ML20086T209 (107)

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{{#Wiki_filter:____ . ~_ 4 NUREG-1435 Supplement 1 I

Stal:us of Safety Issues at l Licensed Power Plants l

TMI Action Plan Requirements Unresolved Safety Issues Generic Safety Issues l U.S. Nuclear Regulatory Commission OITice of Nuclear Reactor Regulation l s..... 3882%8A?! '""PDR 1435 R

6 AVAILABILITY NDTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC pubhcations will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555 2. The Superintendent of Documents, U.S. Government Printing Office, P.O. Box 37082 Washington, DC 20013-7082 3. The National Technical information Service, Springfield VA 22161 Although the listing that follows represents the majority of documents cited in NRC publica-tions, it is not intended to be exhaustive, Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda: NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence! Commission papers; and applicant and hcenace docu-monts and correspondence. The following documents in the NUREG series are available for purchase from the GPO Sales Program; formal NRC staff and contractor reports, NRC sponsored conference proceed-ings, international agreement reports, grant publications, and NRC booklets and brochures. Also available are regulatory guides, NRC regulations in the Code of Federal Regulations, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical information Service include NUREG series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agen y 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. Feceral Register notices, Federal and State leg;slation, and congressional reports can usually be obtained from these libraries. Documents such as theses, dissertations foreign reports and translations, and non-NRC conference proceedings are available for purchase from the organization sponsoring the publication cited. 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. Copies of industry codes and standards used in a substantive manner in the NRC regulatory - process are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, 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,

NUREG-1435 Supplement l' -q l Status of Safety Issues at Licensed Power Plants TMI Action Plan Requirements Unresolved Safety Issues Generic Safety Issues Manuscript Completed: November 1991 Date Published: December 1991 r OfTice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 \\...../

ABSTRACT As part of ongoing U.S. Nuclear Regulatory Comm!ssion (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This 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 safety issues (USis). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSis). This annual NUREG report combines these volumes into a single report and provides updated information as of September 30,1991. The data contained in these NUREG reports are a product of 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 NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TMl Action Plan Requirements, safety issues designated as USis, and GSIs that have been resolved i 1d involve implementation nf an action or actions by licensees. This report makes

information available to other interested parties, including the public. An add'

.., purpose of this NUREG report is to serve as a follow on to NUREG 0933, ".s Prioritization of Generic Safety issues," which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees. I lil -

TABLE OF CONTENTS ABSTRACT,............... ill EXECUTIVE

SUMMARY

vil ABBREVIATIONS.... xl 1 INTRODUCTION.,..... I 1,1 Background 1 1.2 Process and Accountability... 2 1.3 Definitions 4 2 THREE MILE ISLAND ACTION PLAN REQUIREMENTS.. 5 2.1 1mplementation Status........ 5 2.2 Verification Status 9 2.3 Status by Plant. 11 2.4 Status by lssue....., 15 2.5 Conclusions.......... 29 3 UNRESOLVED SAFETY lSSUES 31 3.1 Implementation Status 31 3.2 Verification Status 35 3.3 Status by Plant..... 39 3.4 Status by lssue., 43 3.5 Conclusions....... 47 4 GENERIC SAFETY ISSUES 49 4.1 Implementation Status. 49 4.2 Verification Status 55 4.3 Status by Plant 59 4.4 Status by issue. 63 4.5 Conclusions.. 67 Appendices A Listing of Unimplemented TMI 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 Figures l 2.1 TMl Action Plan Requirements Implementation Status at Licensed Plants -6 2.2 Projected Schedules for Remaln!ng TMI Items ' 7 3.1 Unresolved Safety issues -Implementation Status at Licensed Plants... 32 3.2 Summary of Four Unimplemented USIs... ... 34 4.1 Generic Safety Issues Implementation Status at Licensed Plants . 51 4.2 Summary of Seven Unimplemented GSis.... 53 l l i V

$ ables 2.1 Summary of the Remaining TMI Items by Area......,.... 8 2.2 Summary of the Remaining TMI Items by Plant .,,..,........ 10 2.3 Status of TMI Action Plan Summary by UnM..... . 12 2.4 Status of TMI Action Plan Summary by item ... 16 3.1 Summary of Unimplemented USI Items by Plant . 33 3.2 Summary of USl items Requiring Verification... ..........37 3.3 Status of USl Plants - Summary by Unit. 40 3.4 Status of USl Plants Summary by item..... .... 44 4.1 GSI Numbers and Corresponding SIMS Item Numbers..............,......... 50 4.2 Summary of Unimplemented GSI Items by Plant .... 52 4.3 Temporary Instructions for Resolved GSis................... 56 4.4 Summary of GSI Items Requiring Verification..... . 57 4.5 Status of GSI Plants Summary by Unit.. . f4 4.6 Status of GSI Plants Summary by item. 64 vi l l l

EXECUTIVE

SUMMARY

This NUREG report covers the implementation and verification status of the Three Mile Island (TMI) Action Plan Requirements, unresolved safety issues (USls), and generic 1 safety issues (GSis) at 111 licensed nuclear power plantsi The implementation and ) verification status are current as of September 30,1991. l

Background

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. This annual NUREG report consolidates and updates the information provided in the earlier three volumes. The data contained in these NUREGs are a product of the NRC's Safety Issues Management System (SIMS), which is maintained by the Project Management 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 TMl, USI, and GSI implementation and verification data in SIMS. Three Mile Island Action Plan Reovirements. Volume 1 of this NUREG series reported data on TMI Action Plan Requirements for 114 licensed nuclear power plants, including three plants that are permanently or indefinitely shut down: Rancho Seco, Shoreham, and Fort St. Vrain. For the purpose of this report, the foregoing plants have been excluded from the data on the implementation and verification status of TMl Action Plan Requirements, as well as USIs and GSis. Imolementation Status Approximately 99 percent of the TMI Action Plan items have been implemented at 111 plants. Of the 13,527 applicable items,13,404 have been completed or closed and only 123 remain open from an implementation standpoint. About 50 percent of the remaining 123 open items are projected to be implemented by the end of calendar year 1992. As noted in Volume 1 and in previous reports to the Commission, some slippages nave occurred in projected implementation dates. Delays in the restart of Browns Ferry Units 1 and 3 account for 34 of the unimplemented items. All schedules for implementation of TMI Action Plan items remain within the time frame previously reported to the Commission and to Congress. From an issue perspective, two major areas account for more than half of the 123 remaining items: Detailed Control Room Design Review items (50) and Plant Safety j Parameter Display System items (22). From a plant perspective, the TMI Action Plan Requirements have been fully implemented or closed at 42 of the 111 plants. Four plants account for over one-third of the 123 remaining items: Browns Ferry Units 1,2 and 3 (39 items) and l I Vil i I

San Onofre 1 (6 items). The remaining 65 plants have one or two items each remaining to implement. Verification Status. The NRC must verify a total of 78 TMI issues following licensee implementation. Temporary instructions (Tis) are issued to specify which items are to be inspected and to give NRC personnel special instructions about performing these inspections. The 78 TMl issues that require regional verification have resulted in a total of 6,114 applicable items to be inspected. As of September 30,1991,6,036 items (99 percent) had been verified. Only 78 items remain to be verified, including some items not yet implemented by licensees. Unresolved Safety Issues (USIs) Imolementation Status. Approximately 85 percent of the USI items have been implemented at licensed plants. Of the 1,819 applicable items,1,545 have been completed and 274 remain open from an implementation standpoint. On average, each plant has less than three remaining items to implement, and no plant has more than six items to implement. Four USis (A 9, Anticipated Transient Without Scram; A 44, Station Blackout; A 46, Seismic Qualification of Equipment in Operating Plants; and A 47, Safety implications of Control Systems) account for 91 percent of the unimplemented items. These four USis are in varying stages of NRC review and licensee implementation, as further described in Section 3.1 of this report. Verification StaM. Four Tis have been issued to provide guidance for the field verification of licensee implementation. These Tl designations correspond to USic A 7, Mark i Long-Term Program; A-9, Anticipated Transients Without Scram; A 24, Qualification of Class 1E Safety Related Equipment; and A-26, Reactor Vessel-Pressure Transient Protection, Licensee implementation of A 44, Station Blackout, will also require NRC field verification. The requirements to perform field verifications have resulted _in a total of 429 items to l be verified at the 111 plants As of September 30,1991, the NRC field verification had been completed on 288 (67 percent) of the 429 required items. Generic Safetv lssues (GSis) Imolemertation Status, Approximately 86 percent of the applicable items associated with GSis have been implemented at licensed plants. Of the 2,673 applicable items,- 2,283 have been completed and 390 remain open from an implementation standpoint. ~ On averago, each plant has three to four remaining items to implement, and no plant has more than nine items to implement. - Three plants have implemented all applicable items related to GSIs. Seven GSis account for 95 percent of the items for which ' implementation is incomplete. These GSis are specifically addressed in Section 4.1 of this report, vlil

Verification Status, Seven Tis have been issued to provide guidance for the field verifications of licensee implementation Of the 1,091 GSI items requiring verification, 1,008 (92 percent) have been completed, Conclusions After a detailed review of the implementation and verification status of TMI Action P!3n Requirements, USIs, and GSis, the NRC staff has come to the following conclusions: The NRC closure process for TMl Action Plan issues, USis, and GSis is adequate-for protecting the public health and safety. Licensees continue to make progress in implementing actions imposed or requested by the staff, and the framework exists to verify future implementation of delayed items. The NRC continues to make progress in verifying the _ implementation actic.is reported complete for those issues that require verification. The schedule slippages related to implementing TMI 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 imp;amentation 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, I lx

EXECUTIVE

SUMMARY

This NUREG report covers the implementation and "9rification status of the Three Mile Island (TMI) Action Plan Requirements, unresolved safety issues (USIs), and generic safety issues (GSis) at 111 licensed nuclear power plants. The implementation and verification status are current as of September 30,1991. Backaround t The implementation and verification status of TMI Action Plan Requirements, USls, and GSis was initially reported in Volumes 1, 2, and 3 of NUREG 1435, published in 1991. This annual NUREG report consolidates and updates the information proDided in the earlier three volumes. The data contained in these NUREC4 are a product of the i NRC's Safety issues Management System (SIMS), which is maintained by the Project Management 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, USI, and GSI implementation and verification data in SIMS. Three Mile Island Action Plan Recuirements Volume 1 of this NUREG series reported data on TMI Action Plan Requirements for 114 licensed nuclear power plants, including three plants that are permanently _or indefinitely shut down: Rancho Seco, Shoreham, and Fort St. Vrain. For the purpose of this report, the foregoing plants have been excluded from the data on the - . lmplementation and verification status of TMI Action Plan Requirements, as well as - USIs and GSis, imolementation Status. Approximately 99 percent of the TMl Action Plan items have been implemented at 111 plants, Of the 13,527 applicable items,13,404 have been completed or closed and only 123 remain open from an implementation standpoint.- About 50 percent of the remaining 123 open items are projected to be implemented by the end of calendar year 1992. As noted in Volume 1 and in previous reports to the Commission, some slippages have occurred in projected implementation dates. Delays in the restart of Browns Ferry Units 1 and 3_ account for 34 of the unimplemented items. All schedules for implementation of TMI Action Plan items remain within the time frame previously reported to the Commission and to Congress. From an issue perspective, two major areas account for more than half of the 123 remaining items: Detailed Control Room Design Review items _(50) and Plant Safet'/ Parameter Display System items (22). From a plant perspective, the TMl Action Plan Requirements have been fully implemented or closed at 42 of the 111 plants. Four plants account for over one third of the 123 remaining items: Browns Ferry Units 1,2 and 3 (39 items) and j vli L.

i l San Onofro 1 (6 items). The remaining 65 plants have one or two items each remaining to implement, y.clificat!on Status. The NRC must verify a total of 78 TMl issues following licensee implementation. Temporary instructions (Tis) are Issued to specify which items are to be inspected and to give NRC personn61 specla! Instructions about performing these inspections. The 78 TMI issues that require regional verification have resulted in a total of 6,114 applicable items to be inspected. As of Septemoer 30,1991,6,036 items (99 percent) had been verified. Only 78 items remain to be verified, including some items not yet implemented by licensees. .Unr.e.s.oly.ed Safetyjswes (USls) t Imolementatbn Status, Approximately 85 percent of the USI items have been implemented at licensed plants. Of the 1,819 applicable items,1,545 have been. completed and 274 remain open from an implementation standpoint. On overage, each plant has less than three remaining items to implement, and no plant has more than six items to implement. Four USIs (A 9, Anticipated Translent Without Scram; A 44, Station Blackout; A 46, Seismic Que!ification of Equipment in Operating Plants; and A 47, Safety implications of Control Systems) account for 91 percent of the unimplemented items. These four USIs are in varying stages of NRC review and licansee imp!amentatior., as further described in Section 3.1 of this report. yerificationSlatus. Four Tis have been issued to provide guidance for the field verification of licensee implementation. These Tl designat'ons correspond to USls A 7, Mark i Long Term Program; A 9, Anticipated Transients Without Scram; A 24, Quahfication of Class 1E Safety Related Equipment; and A 26, Reactor Vessel Pressure Translent Protection. Ucensee implementation of A 44, Station Blackout, will also require NRC field verification. The requirements to perform field verifications have resulted in a total of 429 items to be verified at the 111 plants. - As of September 30,1991, the NRC field verification had heen completea on 288 (67 percent) of the 429 required. items. Beneric Safety issynsjG'ils) Implement 01!onflatus. Approximately 86 percent of the applicable items associated with GSis have been implemented at licensad plants. Of the 2,673 applicable items, c 2,283 have been completed and 390 remain open from an implementation standpoint. On average, each plant has three to four remaining items to implement, and no plant. has more than nine items to implement. Three plants have implemented all applicable items related to GSis. Seven GSis account for 95 percent.of the items for which Implementation is incomplete. These GSis are specifically addressed in Section 4.1 of - this report. -I vill J . _.,... ~,,. _ ~

... _ _ _ _.._ ~ - i Venficailon Status. Seven Tis have been issued to provide guidance for the field verifications of licensee implementation. Of the 1,091 GSI items requiring verification, i 1,008 (92 percent) have been completed. How'Jsions I l After a detailed review of the implementation and verification status of TMI Action Plan Requirements, USis, and GSis, the NRC staff has come to the following conclusions: l The NRC closure process for TMI Action Plan issues, USIs, and OSIs is adequate for protecting the public health and safety. Ucensees continue to make progress in implementing actions imposed or { requested by the staff, and the framework exists to verify future implementation of delayed items. The NRC continues to make progress in verifying the implementation actions reported complete for those issues that require verification. l The schedule slippages related to implementing TMI Action Plan items do not pcss 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 TMl requirements are completed in accordanco with regulatory requireri,ents and within acceptable time frames, j L l lX .. ~. _., _ -,... - ~

i ABBREVIATIONS ACRS Advisory Committee on Reactor Safeguards ATWS anticipated translent without scram B&O Bulletins and Orders J B&W Eabcock and Wilcox BWR boiling water reactor CE Combusti, ' Engineering ECCS emergency core cooling system GIP Generic implementation Procedure GL generic letter GSER Generic Safety Evaluation Report GSI genotic safety issue MPA mult! plant action NRC U.S. Nuclear Regulatory Commission NRR Office of Nuclear Reactor Regulation (NRC) PWR pressurized water reactor RHR residual heat removal SIMS Safety issues Management System SPDS safety parameter display system SSER Supplementary Safety Evaluation Report Tl temporary instruction TMI Three Mile Island USl unresolved safety losue 1 xi

1 INTRODUCTION This annual NUREG report updates the implementation and verification status of the Three Mile Island (TMI) Action Plan Requirements, unresolved safeiy issues (USIs), and cene@ safety issues (GSis). The NRC previously published three volumes of this NURES *eries. Volume 1, published in March 1991, discussed the status of TMl Actio i Plar Requirements. Volume 2, published in May 1991, identified the impieh,mdation and verification status of actions associated with USIs. Volume 3, published in June 1991, detailed the status of GSI actions. This annual NUREG report combines the information initially reported in Volumes 1,2, and 3, and includes information through September 30,1991. Subsequent volumes will be published annually to document the progress of implementation and verification c! these items. This report describes the implementation and verification status at tho 111 licensed i nuclear power plants in the United States and makes this information available to interested parties, including the public. Volume 1 of this NUREG series reported data on TMl Action Plan Requirements for 114 plants, including 3 plants that are permanently or indefinitely shut down: Rancho Seco, Shoteham, and Fort St. Vrain. For the purposes of this report, the foregoing plants have been excluded from the data on the implementation and venfication status of TMl Action Plan Requirements, as well as USIs and OSIs. Included herein is information on the implementation and verification status of the TMI Action Plan Requirements, USts, and GSis. For the 111 plants, there are 13,527 applicable items for TMI Action Plan issues,1,819 for USIs, and 2,673 for GSIs. A total of 18,019 applicable items are addressed in this report. The information presented in this volume is current as of September 30,1991. 1.1 .Bachgtogld TMl Action Plan Requirements, USIs, and GSIs are ail types of generic issues that originated from increased technical understanding of the safety of nuclear power plants. This increase in such knowledge 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 were discussed in Volumes 1 through 3 of this NUREG series. Actions to be taken by licensees in response to these generic Issues apply to more than one plant. The NRC evaluates licensees' implementation status in conjunction with its evaluation of other NRC requirements, unique plant considerations, and interim measures. Similarly, the NRC authorizes a plant to restart or begin operation 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, that has not fully implemented allitems 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 We public health and safety. 1

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 Staff in the Office of Nuclear Reactor Regulation (NRR) and by NRC regional personnel. The NRC has given elQnificant attention to the quality review of TMI, USl, and GSI implementation and verification data in SIMO. 1.2 flocass and AccoMDiabili.ty In 1989, the Commission adopted a six step program f jr 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 USts and GSis. The. overall NRC program consists of the following steps: l J@ntifyina Relevant Issun - Generic concerns are typically identified by the 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 iden.ried by others, for example, licensees, vendors, the Advisory Committee on Reactor Safeguards (ACRS), and the public. The NRC staff identified the TMI requirements by cornpiling and evaluating information from all available sources concerning the accident at TMI. Prioritizing issun - Once identified, an issue is evaluated by the staff for its potentialimportance 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 a those safety issues that have a high potential for reducir.g 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. Resolving issues - The staff evaluates corrective actions that might be taken 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 woik 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. Jmposina Reagirements (USIs and TMI Action Plan Recuirements)- Each 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 iss'. 3, or if the required corrective actlans should be backfit to existing plants. 2 -,.,y,'.s. o n y..,.ymn.-e,.e,w.y e n s,v e r.re r,. --%.y m.- , www r y-. r--. ...,m.% y-,, -wy ,m 3-,- 1w-r-. n.

- __-- - - _ _~ Benuesting Action (QSls)- The NRC staff evaluates the importance of an 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 multi plant action (MPA) number for tracking purposes. trnplementing Actions - Licensees of affected plants take corrective actions to satisfy commitments made in response to the imposed requirements (TMl Action Plan Requirement, and USts) or the staff's request (GS!s). These actions may include modifications or additions to equipment, structures, procedures, technical specifications, operating instruction? and so forth. l The role of the NRC 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 Plan 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 plant. The Project Manager monitors licensee progress toward closure and ensures that the work is completed by the negotiated date. The Project Manager ensures that the status of the item is properly documented for each plant. Yefifyjag implementdon - NRR staff members, NRC regional offices, and NRC resident inspectors ensure that licensees meet commitments made to the NRC for those issues requiring verificetion. Temporary instructions (Tis) have been issued to guide inspectors in verifying licensee implementation of corrective actions for certain genene 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. The Safety issues Management System (SIMS) is designed to track issues from their identification through implementation of associated actions cnd field verifichtlon, The NRC Project Manager periooically 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 be accompanied by a reference document from the 3-w. a.-

l licensee staff r>roviding the basis for closure of the issue at the par 1icular plant, and (2) the inspection report number and the date of the inspection be entered into SIMS If verification is required. 1.3 DeflD111Q05 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 (GS1)- 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 plants. Jamlemented.ltem - An itern is implemented when a licensee has completed the activities necessary to satisfy the requirements (or assumptions) made in the staff's technical resolution in accordance with commitments concerning the generic issue. llem - The application of a TMI Action Plan Requirement, USl, or GSI to a specific plant. IM12ntion Plan itse - An issue applicable to one or more licensed plants as derived from NUREG-0737, Supplement 1 thereto. 1Q101 Plant itemji - The theoretical maximum number of potential items resulting from applying each issue (TMI, USl, or GSI) to all 111 plants. Total Acolicable Plant items - The total number of applicable items, determined by reviewing the applicability of each issue at each of the 111 plants. Unimolemented item - An item is unimpirmented when a piant has not completed the activities necessary to satisfy the actions requested or required by the staff following the resolution of a particular generic issue. .Unte1Qhed Safety Ismg_(Ujj)- An unresolved safety issue is a matter affecting a riumber of nuclear power plants that poses important questions concoming the adequecy 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.

• y.enfication Comoteted - A licensee's actions to implement a technical resolution for a generic issue have been inspected and verified by the NRC in accordance I

with the guidance provided by the applicable temporary instruction for that issue. - 4,

1 l 2 THREE MILE ISLAND ACTION PLAN REQUIREMENTS This section describes the overall status of implementation and verification of Three Mile Island (TMI) Action Plan items at the 111 currently licensed nuclear power plants. Volume 1 of NUREG 1435 repc,rted the status of 114 licensed plants, including data on 3 plants which are permanently or indefinitely shut doivn: Rancho Seco, Shoreham, and Fort St. Vrain. For the purposes of this report, these 3 plants are not included in the data on the implementation and verification status of TMl Action Plan l Requirements. l 2.1 ,[mn!cmontation Status Approximately 99 percent of the TMI Action Plan items have been implemented or closed at licensed facilities. Of t% 9,527 items,13,404 have been completed and only 123 have not yet been implementM Figure 2,1 presents the overall status of implementing the TMl Action Plan Requirements. The 13,404 ltems completed at the 111 plants have been disposed of as follows: A total of 13,004 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 400 items have been superseded and the associated requirements have been effectively addressed by other items or through other regulatory means, Tho superseded items are discussed in detailin Volume 1 of NUREG 1935. I With respect to the remaining 123 unimplemented items, the following observations are made: Approximately 50 percent of the remaining 123 open items are projected to be implemented by the end of calendar year 1992, as shown in Figure 2.2. Ucensees continue to make progress toward implementation of the remaining open items, As noted in previous status reports, some slippages have occurred in projected impleinentation dates, Delays in the restart of Browns Ferry Units 1 and 3 (34 items), along with the rescheduling of refueling outages at other plants, account for a large number of the slippages in the implementation of remaining TMI items Browns Ferry Unit 1 has 15 TMl items that will not be implemented until the end of calendar year 1996. All schedules for implementing the remaining TMI Action Plan items are within the time frame previously reported to the Commission and to Congress. From an issue perspective, two raajor areas account for about 59 percent of the 123 remaining items, as shown in Table 2.1: Detailed Control Room Design - Review items (50) and Safety Parameter Display System items (22). 5

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PROJECTED SCHEDULES FOR REMAINING TMI ITEMS ITEMS NOT IMPLEMENTED AT END OF CALENDAR YEAR l l i 200 - t JUNE 1989 SCHEDULES l l CURRENT o 150 SCHEDULES l 5

E 123

~ l Sp 100 99 E I a a e b l t 62 t 57 50 - 31 0 0 0-l l } l '{ { g 0991 1191 12,92 1193 12S4 12S5 1196 NO DATE 09 S1 12S1 1192 1193 1194 1295 1296 NO DATE JUNE 1989 SCHEDULES

• 80 57 31 19 15 14 12 12 Ca>JOS1 SCHEDULES
• 123 99 62 22 17 15 0

b

• Based on dates of item listed as not implemented Figure 2.2

I { i

SUMMARY

OF THE REMAINING TMi ITEMS BY AREA l-l- AREA OPEN f I f o Plant SPDS Console 22 i-t j o Post-Accident Sampling 7 j o Relief & Safety Valve Test Report 6 O Containment Isolation Dependability 4 I o Accident Monitoring 10 6 4 o instrumentation for Detection of inadequate Core Cooling 8 l 1 o B&O Task Force issues 8 o Control Room Habitability 3 f i I o Technical Specifications - NUREG-0737 5 i h j o Detailed Control Room Design Review 50 l l l TOTAL 123 f Table 2.1 t t

From a plant perspective, the TMl Action Plan has been fully implemented or closed at 42 of the 111 plants. Table 2.2 Summarizes the 123 unimplemented items by plant. Four plants account for over one third of the remaining 123 items: Browns Ferry 1,2, and 3 (39 items) and San Onofre 1 (6 items). The remaining plants have no more than 2 items remaining to implement. Appendix A lists the unlmplemented TMI items by issue and gives projected implementation dates. 2.2 ytrification 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 actions 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 reouirernents. 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 TMI requirements, which cover a total of 6,612 items at the 111 plants. Upon initialinspection of certain items and further review by the regional offices,498 items covered by the Tis were found to be inapplicable from a verification standpoint, leaving a net total of 6,114 ltems 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 30,1991,6,036 items (99 parcent) had been verified. Only 78 items remain to be verified, including some items not yet implemented by licensees. i 1. l ?9

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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 comp:eted, 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 gives projected implementation dates. From an implementation standpoint, the IMI Action Plan has been fully implemented at 42 of the 111 plants. Four plants account for over one third of the 123 remaining open items: Browns Ferry Units 1,2, and 3 (39 items) and San Onofre 1 (G ltems). From a verification standpoint, all required inspections have been completed at 67 of the 111 plants. Browns Ferry Units 1 and 3 have 10 items each thrit will require verification following implementation by the licensee. Forty two plants have one to five items that remain to be verified. i 11-

l i e R-kUFEG-001 SAFETY I55UE MANAGEMENT SYSTEM PAGE 1 l ) STATUS OF TMI ACTION PLAN -

SUMMARY

SY UNIT 1 IMPLEMENTATION VERIFICATIDW i I i j ITEMS ITEMS PE R CENT ITEMS ITEMS ITEMS ITEMS PER CEmT UNIT APPLICABLE COMPLETED COMPLETED FEMAINING WEQUIRED APPLICABLE COMFLETED COMPLETED i i ARKANSAS 1 122 121 l99 1 1 62 61 80 198 '1 i ARKANSAS 2 112 111 ' 99 l 1 59 58 56 I st l BEAvtR VALLEY 1 117 116 99 t 1 E2 51 81 1 10, 4 BE AVER VALLE Y 2 126 126 1 100 O 62 ST ST I 100 I SIG RDCM POINT 1 304 103 1 89 l 1 55 50 50 1 100 i 1 TRAIDWOOO I 26 128 i 100 O 62 56 58 l 100 l 1 .,RAIDWOOD 2 .8 125 l 99 l 1 62 56 SS i 100 BRDWNS FERRY 1 110 95 (88 l 15 ST 51 41 I so 1 BRDWNS FERRY 2 119 105 1 95 5 57 51 50 I sa BROWM3 FERRY 3 110 51 1 82 19 SF $1 41 I se BRUN9dICM 1 110 109 98 1 57 51 51 1 ISO BRUNSWICR 2 110 108 '99 1 ST 51 51 1 100 BYRO4 1 125 128 . 100 0 82 58 58 1 100 t 8VROM 2 128 129 - 100 1 0 82 58 58 l 1GO CALLAWAY ! 123 123 101 0 CS SS 50 1 100 t ^ CALVFRT CLIFFS 1 113 112 ' 99 1 SS 53 53 l 100 i i rf CALVERT CLIFFS 2 113 112 1 99 1 SS 53 53 1 100 CATAWBA 1 128 128 i 100 i S 52 SS 59 ' 33 t CATAWBA 2 128 126 l 100 0 82 82 81 ss CLINTCw 1 120 120 1 100 t 0 58 58 58 J100 t CDMANCHE PEAK 1 11s 119 i 100 i 0 55 se 47 s3 i COOM 1 117 117 l 100 l 0 62 55 35 !!90 COCM 2 117 118 I 99 l 1 82 55 55

100 COOPER STATION 116 108

98 l

2 57 SL-51 1 10S CRYSTAL RIVER 3 122 120 1 97 i 2 82 59 54 se 4 i DAv1S-8 ESSE 1 121 121 ' 100 0 81 55 54 i es OIABLO CANYC# 1 128 125 - 89 1 81-55 55

100 DIABLO CANYO4 2-128 125 99 1

1 81 ST ST ' 109 l DRESDEN 2 110 100 l 99 .I 1 55 52 51 1 et 99 I 1 53 52 51 1 SS ORE SDEN 3 110 109 0 SF 5e se i 140 DUANE ARMOLD 110 110 1 100 i FAPLEY I 118 116 1 95 2 62 55 56 1 100 FARLEY 2 123 128 (98 2 62 SS 56 1 100 FERMI 2 120 118 1 99 1 58 50 43 1 85 l FITZPATRICK 119 110 1 100 1 0 57 59 SS i SS ) I FORT CALNGU4 1 113 112 1 99 1 59 55 50 l 80 l GIMMA 116 116 l 100 0 31 59 56 l 100 t GRAND CULF 1 120 120

100 1

0 56 59 50 I tOS HADDAM WECM 11T 115 l 95 l 2 82 55 53 1 98 HARRIS 1 125 125 l 100 l 0 $1 50 60 i 100 MATCH 1 110 1^3 1 99 i 1 57 57 ST

100 J

HATCH 2 110 109 i S9 i 1 57 57 56 I 98 i . MOPE CEEEM 1 120 120 1100 1 0 58 50 50 1 100 I IEJIAN POINT.2 118 a18 (100l 0 62 58 59 l 100 L I Table 2.3

1 I R-NUREG-001 SAFE 7Y ISSUE MA4AGEMEM T ST STEM PAGE 2 f i STATUS CF TMI ACTION PLAN - S M 9tPV e1Y UNIT i IMPLEMENTATICN VEEIFICATICN [ Uw!T APPLICABLE COMPLETED COMPLETED REMAINING REQUIRED APPLICAELE COMPLETED COMPLETED INDIA 4 POINT 3 117 117 1'99100) O 42 59 59 r100)

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97 i

I MILLsTDME 2 113 112 '99 3 0 59 54 54

100 f

MILLSTOWE 3 127 127

100 0

52 SS 53 i 100 L i MouTICELLO 110 110 100 0 57 51 51 1 100 t s NINE MILE POINT 1 107 105 l 98 2 58 54 Se 100 l mime MI' E POINT 2 119 119 l 100) e 55 52 52 L100 t [ 4 ~^ WORTH AWMA 1 118 117 1 99 P 1 62 60 60 100 t l W WORTH Asps 4 2 128 127 [ ! 99 f 1 82 80 69 1 100 i i OC0 HEE 1 122 121 99 1 62 57 56 1 98 f } OCO.6EE 2 122 121 . 99 i a 62 55 57 l SS t OCOWEE 3 122 121 (ED 1 62 58 57 i SS t l OYSTER CREEK 1 107 108 199 ) 1 ss 47 47 l 1003 PALISADES 113 112 (89 i 1 59 51 51 1 18e l PALO VEPDE 1 120 119 (99 1 59 52 52 ! 100 PALO VERDE 2 120 119 . 99 1 59 53 53 1 100 i PALO VERDE 3 120 119 i 99 O 57 51 50 l St 1 59 54 54 1 100 l i PE ACM BO T TOM 2 110 lie 1 100 PEACM BOTTOM 3 110 110 1 100 l O $7 51 50 l SP 1 i-PERRv 1 120 170 1 100'l 0 38 55 55 F190 t a i PILGRIM 1. 110 109 i 99 t 1 57 et 43 (100) FOINT BEACM 1 117 118 1 99 1 62 56 55 l'190 I i POINT BEACM 2 117 116 ' 99 l 1 82 SS 55 l 100 I i PR AIR IE ISLAND 1 117 118 1 99 1 82 52 52 l 100 PRAIRIE ISLAND 2 417 116 l 99 1 62 53 53 i 109 QUAD CITIES 1 110 tot i 99 1 57 51 50 '. 98 L i QUAD CITIES 2 110 109 1 99 l 1 57 51 50 i 93 i RIVER BEND 1 119 119 . 100 I O $5 SS 47 ' S3 i t ROSIWSON 2 117 116 , 99 l 1 82 58 54

SS l

l SALEM 1 Its 115 1 99 l 1 61 54 52 (St 4 i SALEM 2 127 128 (99 l 1 52 57 55 (9s L SAN cworRE 1 Its 110 1 94 t a s1 5: 5s (#s j ' SAM Om0FRE 2 122 120 'i 95 2 59 53 53 t100 SAN OwCFFE 3 128 120 i SS 2 59 55 55 (100 SEA 8800M 1 127 127 (200) 8 82 57 55 (88 SEQUOYAH 1 127 a25 (29 1 1 52 58 55 195,1 Table 2. 3 i t i i n mi.

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2.4 .Sjatus by issue Table 2.4 summarizes information on each TMI issue. For implementation, the table shows the number of applicable plants, the number of plants completed, the percentage completed, and the number of plants remaining. For verification, the table l shows whether the issue requires verification, the number of plants covered by the TI, the number of plants requ! ring verification, the number of plants completed, and the 4 percentage completed. Of the 172 TMI Action Plan issues,143 have been fully implemented and 4 have been superseded. Two categories of TMl Action Plan issues account for about two thirds of the TMl requirements to be implemented: Detailed Control Room Design Review, with j 50 items with implementation yet to be completed and the Safety Parameter Display System, with 22 iterns remaining to be completed. The next largest contributors are Accident Monitoring, with 10 plants yet to complete implementation, Bulletins and Orders (B&O) Task Force issues, still open at 8 plants and Instrumentation for Detection of inadequate Core Cooling, with 8 plants yet to complete implementation. Of the 78 TMI Action Plan issues requiring verification,51 have been completed,25 issues must ce verified at 1 to 4 remaining plants, and two issues must be verified at 13 or more remaining plants. i 3.. .. ~ -.- -. .. -.. = - - -

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i l t l i t R.NuREG.042 SAFETY YSSUE MANAGEMENT SYSTEM ME S t STATUS OF TMI ACTIDW PLAN - SubstARY SY ITEM IMPLEMENTATION VERT *ICATION I .== - -............ -_ ........= __-- y PLANTS UNITS PER CEmi tMITS UNITS tmITS PER CE NT ITEM APPLICAeLE COMPLETED COMPLETED REMAIN 1hG REQUIRED APPLICAeLE COMPLETED COMPLETED =- II.E.1.1.2 71 73 (1903 0 YES 73 73 (190) AFS EVALUATION. SHORT TERM MODS. II.E.1.1.3 74 74 (180) 0 YES 74 ya Igg,I AFS -LONG TERM MODS. II.E.1.2.1.A es es lle0) S YES es es (19e3 AFS INITIATION & FLOW-CONTROL GRADE t II.E.1.2.1.8 74 74 (190] C YES 74 74 (1es) AFS IMITIATION & FLOW - SAFETY ORADL ) II.E.1.2.2.A se se 110o3 0 TES se se fleep i AFS INITIATION & FLOW - FLOW IleUCTION CONTROL GRACC 1 I " b II.E.1.2.2.8 74 74 (1901 0 NO (3 ATS INITITATION & FLOW - LL CAT A TECH SPECS. l I j. II.E.1.2.2.C 74 74 (2001 e YES 74 74 (19e3 AFS INITITATION & Flew - SAFETY GRADE 4 II.E.3.1.1 74 74 (10s) e YES 74 74 (1903 v i. EMRGENCY POWER FOR PRESSURIZER MATERS - UP9RADE POWER SUPPLY r II.E.3.1.2 74 74 fles) e 3a EMAGENCY POMR FOR PRESSURIZER MATERS - TECH SPEC 1 i II.E.4.1.1 11e 11e (see) 0 NO DEDICATED MYDROGEN PENETRATIONS - DESIGN II E.4.1.2 110 110 (1 col e YES 105 103 fee DEDICATED MYDROGEN PE ETRATIONS - REVIEW & REVISE M2 C04tTROL PROC j II E.4.1.3 110 110 (100) 4 YES 1e7 104 feT I i [ DEDICATED MYDROGEN PENETRATION - INSTALL f II.E.4.2.1-4 111 10e tes ) 2 YES 111 110 tee i i CONTAIMENT ISOLATION DEPEleASILITY - IMP. DIVERSE ISOLATION II.E.4 2.5.A 111 til (183) e M0 CONTAllp4ENT ISOLAT. DEPEseABILITY. CNTMT PRESS. SETPT. SPECIFY PRESS. t i II.E.4.2.5.8 111 111 f100' e YES 110 les les j l i CONTAINMENT ISOLATION DEPEseASILITY - CNTMT PRESSUPt SEtM. Moos. Table 2.4 4 k 4 i - ~ - -s

l. k i l t lt .t 'R-NUREG-002 5ATETY ISSUE M A N A G E. M E N T SYSTEM PA9t S t 3 STATUS OF TMI ACTIDM PLAN

SUMMARY

SY ITEM l I t IMPLEMENTATIDW VERIFICATION l 1. } PLANTS UNITS PER CE NT UNITS UNITS UNITS 4 CENT E I. ITEM APPLICA8LE COMPLETED COMPLETED REMAINING REQUTL D APPLICABLE COMPLETED

• LETED 1

3-l II.E.4.2.8 111 110 199 1 YES 110 109 s99 3 l CONTAINMENT ISOLATION DEPENDA81LITY - CNTMT PURGE VALVE s 5 1 II.E.4.2.7 111' 111 (200) O YES Jos 104 (Se } CD'ETAIsNENT ISOLATION DEPENDA81LITY - RADIATIOM SIGNAL CW PURGE VALVES t i. t i.. II.E.4.2.8 til 110 ISS 1 1 NO CONTAIMMENT ISOLATION DEPENDA81LITY - TECM SPECS j I II.F.1.1 . III ISS (St i 2 NO . ACCIDENT-MONITORING - PEOCEDURES i !!.F.1.2.A 111 los 19s 1 2 YES 111 111 (2003 l ACCIDENT-MONITORING - NOOLE GAS MONITOR i-i DO 'II.F.1.2.5 til 109-(98 1 2 YES 111 118 199 1 7' ACCIDENT-MONITORING - 10 DIRE / PARTICULATE SAMPLING l ,4 TI.F.1.2.C 111 189 (98 ) 2 YES 111 109 (94 3 ACCIDENT-MONITORING - CONTAIsNENT HIGM-RANGE MONITOR f II.F.1.2.0-til 110 (99 1 1 YES 111 les (98 ) [ ACCIDENT-MONITORING - C04TAIINENT PRESSURE i II.F.1.2.E ~ 111 110 (99 ) 1 YES 111 111 (2003 i ACCIDENT-MONITORING - CONTAINMENT WATER LEVEL 3 g. II.F.1.2.F 111 111 (190) 0 YES 119 109 (99 ) ACCIDENT-MDMITORING - CONTAINMENT HYDROGEN t II.F.2.2' 74 74 f1001 0 YES 74 71 (95 3 INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING - SUSCCCL METER I II F.2.3-111 110 (99 I a NO i INSTRUMENTATION FOR DETECT. DF INADEQUATE CORE C00 TING - DESC. OTMER i l' II.F.2.4 110 103 193 3 7 YES 197 g4 (37 3 INSTRMNTATM FOR DETECTS OF INADEQ CDRE CL.NG INSTLL ADD *L INSTRMNTATM r 11.3 1.1-74 74 (100) 0 YES 74 73 (93 } l j' POWER SUPP. FCR PRESSURIZER RELIEF,8 LOCK VALVES & d VEL IND.- UFCRADE l: II.G.1.2 74 74 (200) 0 NO POWER SUPP. FOR FRESSURIZER RELIEF. BLOCK VALVES & LEVIE IMD.- TECM SP, 2~ l l Table 2.4 l, i l i k i ~

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l i e I I l i R-NUREG-002 SAFETY ZSSUE MANAGEMEmT SYSTEM PAGE 9 STATUS OF TMI &CTICf! PLAN - SUPE 9ARY BY ITEM IMPLEMENTATIOM VERIFICAT10g I ................................~.............m. PLANTS UNITS FT R CE ft* UwiTS UNITS UWITS PER CTui ITE>r APPLICABLE COMPLETED COMPLETED REMAINING REQUI8ED APPLICA5LE COMPLETED CDMFt.E TED l II M 2 9 / 7 (1001 0 YES T i (190) ORDERS CM B&nd PLANTS. FEMA CM ICS .i II K.3 1 A ?4 T4 {100) 40 B&O TASM FORCE - AUTOMATIC PORY ISOLATI0m DESIGN { II R.3 1 8 74 74 (1001 0 YES 64 64 (1001 FINAL RECDP91ENDATIONS.8&O TASR FORCE. AUTO PCRV ISO TEST / INSTALL ? i II K 3_10 46 46 (20S! O YES 42 42 (100) f B&O TASM FORCE - PROPOSED ANTICIPATORY TRIP MODIFICATIONS II.K 3.11 '9 9 (100) S s' B&O TASK FORCE - JUSTIFY USE OF CERTAIN PCRW II.R.3 12 A 52 52 (100) 0

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to 840 TASM FORCE - ANTICIPAT0tY TRIP OE TUR81ME TRIP PROPOSED MOOS b II.K.3.12 B 52 52 (lost 0 YES C' 49 (1603 840 TASK FORCE - ANTICIPATORY TEIP DE TUR91ME TRIP INSTALL MOOS. i II M.3 13 A 33 33 (2001 0 No 840 TASK TORCE - HPCI & RCIC SYSTEM IWITIATIDM LEVELS ANALYSIS l II.M.3.13 8 33 31 193 1 2 YES 33 33 (100) B&O TASM FORCE - MPCI & RCIC IMITIATIC4 LEVELS MODIFICATI04 II.K 3.14 5 6 (1003 0 YES S S (100) S&O TASM FORCE.- ISO ConDEwSER ISOLATIO4 P2 HIGH RAD II.K.3.15 33 33 2001 0 TES 33 33 (1001 B&O TA$r. FORCE - MODITY 90CI 4 RCIC BRK DETECTION C(RCUITRY l I II K.3.16 A 37 37 (100) 0 NO [ S&C TASM FORCE - CHALLENGE & FAILLME OF RELIEF WALVES STUOY TT_W.3.15.8 37 37 (2003 9 YES 37 37 (2001 B&O TASM FORCE - CHALLENGE & FAILtME OF *ELIEF VALVES N001FICATIows II.K.3.17 sr 37 (2001 o no B&O TASK FORCE - ECC SYSTEM OUTAGES i II M.3 13.A 36 39 (2001 0 NG [ B&O TASK FORCE - ADS ACTUATION STUbY i i Table 2.4

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i R-NUREG-002 SAFETY ISSUE MANAGEMENT SYSTEH PACE 11 l' l STATUS OF TMI ACTION PLAN -

SUMMARY

37 ITEM k i l IMPLEMENTATION VERIFICATION ...... - _..... - _..... _ _... ~ _. - _ ---....... g DLANTS-UNITS PER Cr e ? ' UNITS UNITS UNITS PER. CEN1 i _.---- -= C0K'LE *t'.s REM 4INING REQUIRED APPLICABLE COMPLETED' COMPLETED ITEM APPLICABLE COMPLETED i II.K.3.3. "til 111 (100$ 0 ho B&O TASM 3RCE.- REPORTENG SV & RV FAILURES AND CHAla.ENdES ' i II.R.3.30.A til til (102) O PG I C&u TASK FORCE - SCHEDULE FOR OUTLINE OF SE LP' - P;.10EL B&6 i SK F RCE- - SS LOCA MODEL. JUSTI ICAr" H II.X.3.30.C 111 111 (100) 0 NO B&O. TASK FORCE.- 58 LOCA NETHODS NEW ANAlfSES r II.K.3.31' 111 111 (1C01 0 NO B&O TASK FORCE - COMPLIANCE WITH CFR 50.48 1 h3 II.K.3.44 '37 37 (190) 0 NO CD .B&O TASK FORCE - EVALUATE TRARSIENT WITH SINGLE FAILuti 'f II.K.3.45 3M. ~8 4100) 0 NO l l. B&O TASK FORCE - ANALYSES TO SUPPORT II.K 3.46 37 37 (100] 0' WO RESPONSE TO LIST OF CONCERNS FROM ACMS CONSULTANT II.K.3.5.A 74 - 74 (1001 0 NG I B&O TASK FORCE - AUTO TRIP OF RCP*S PROPOSED MODIFI M TIONS [ i II.K.3.5.s 74-74 (1001 0 YES se s+ (100) B&O TASK FORCE - AUTO TRIP OF ACP*S MODIFICAYIONS t i II.K.3.5T 23 23 f_00) 0 YES-23 2x (86 ) IDENTIFY WATER. SOURCES PRIOR TO MANUAL ACTIVATION M ADS 5 II.K.3.7 7 7 (100) 0 NO 840 TASK. FORCE - EVALUATION OF'PORV OPENING PROSABILITIEs II.K.3.9 52 52 (1bo) 0 YES 52 $2 (100) B&O TASK 90RCE 'PID CONTROLLER MODIFICATION MPA-F008 111 til (100) 0 NO I.D.I.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN _ p MPA-F063 111 111 (100) 0 YES 37 37 (100) III.A.1.2 TECHNICAL'SUPPDRT CENTER' t Snatile 2.4 i ri i =

4 I i l R-NUREG-002 ~ SAFETY ISSUE 4 A I' e.

• A NT 5YSTEM N E 12 s

STATUS OF TMI ACTAL_ i w - St>#4ARY BY ITEM i i e

• .ACMTATION VERIFICAT1088 PLANTS OPTTS PER CENT UNITS UNITS UNITS PER CENT E

ITEM APPLICABLE COMhtETED COMPLETED PEMAINING REQUIRED n?PLICABLE COMPLETED COMPLETED t MPA-F064 111 112 (1001 0 YES 31 51 (103) III.A.1.2 GPERATIONAL SUPPORT CEKTER s MPA-F065 til til (100 0 YES 39 38 (100) III.A.1.2 EMERGENCY OPERATIONS FACILITY MPA F071 111 81 (54 ) S0 ro I.D.1.2 DETAILED CONTROL ROOM REVIEW IFOLLOWUP TO F-8) + NN e L -I 5 ) h 9 i L l I 4 Table ?. 4 i i i a .. x

l 2.5 Conclusions After a deta 3d review of the implementation and verification status of the TMI Action Plan Requirements at alllicensed plants, the NRC staff has concluded the following: Substantial progress has been made in the implementation el TMI Action Plan Requirements improvements at alllicensed plants. Licensees continue to make progress toward implementing the remaining requirements. The schedules cerently proposed by licensees for completing the remaining items are generally acceptable and are within the time frames given to the Commission and to Congress. 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 schedules proposed by licensees to ensure that the TMl requirements that remain to be implemented are completed in accordance with regulatory requirements. 3 UNRESOLVED SAFETY ISSUES I This section presents the overall status of implementation and verification of the requirements imposed following the resolution of unresolved safety issues (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 requirementa at licensed plants. The information presented here includes all USl items related to the 111 licensed nuclear power plants considered in this report. Approximately 85 percent of the USI items have been implemented at " censed plants. Of the 1,819 applicable items,1,545 have been completed and only 274 remain open from an implementation standpoint, On average. each plant has less than three remaining items to implement. No plant has more than six remaining items. Figure 3.1 presents the overall status of, and progress on, USls. Of the 111 plants, none have fully implemented all applicable USis. Table 3.1 lists the number of-unimplemented items by plant. Appendix B lists the unimplemented USl items by issue and gives projected implementation dates. USls A 9, A-44, A-46, and A-47 account for 91 percent of the 274 unimplemented items. Figure 3.2 sumniarizes the implementation status of thnse issues. These four USIs are in varying stages of NRC review anJ implementation, as described below. A-9 Anticioated Transient Without Scram Most operating reactors have installed systems to comply with the anticipated transient without scram (A'iWS) rule. Some of the plants listed as having unimplemented items have systems that are installed and operable but that may still require modification or inclusion of a design aspect to fully comply with the AW/S rule. Examples of some remaining issues that require resplution before full imphmentation at some plants are diversity of the Rosemount trip unit and diverse auxikary feedwater actuation. A 44 Station Blackout The station blackout rule was issued in July 1988. The licensees' responses addressing the rule were due within 270 days. _ According to the rule, licensees are required to implement their proposed modifications (hardware and procedural) within two years of NRC notification approving the lipnsee's approach. The staff has completed approximately half of the safety evaluation reviews of licensee responses. Most of these responses are for plants that have proposed major hardware modifications. The remaining plants are expected to implement minor _

) Unresolved Safety issues implementation Status at Licensed Plants l 2000 1500 -- 181 1545 500 -- 0-l Appilcktie Imptomected Unlmplemented Figure 3.1 l l -

Summarv of UnimDISmented USI items by Plant f lle m s items items PLANT Remaining PLANT Flamaining PLANT Remaining Arkansas 1 3 Haddam Neck 3 Prattle Island 1 2 Arkansas 2 3 Harris 1 1 Pralrie Island 2 2 Beaver Valley 1 2 Hatch 1 3 Quad Cities 1 4 Beaver Valley 2 1 Hatch 2 4 Quad Cities 2 4 Big Rock Pt 1 3 Hope Creek 1 1 River Bend 1 2 Brridwood 1 1 Indian Pt 2 2 Robinson 2 3 Braldwood 2 1 Indian Pt 3 3 Salem 1 2 Browns Ferry 1 6 Kewaunee 3 Salem 2 2 Browns Ferry 2 3 LaSalle 1 3 San Onofre 1 3 Browns Ferry 3 6 LaSalle 2 3 San Onofr.- 2 3 Brunswick 1 2 Limerick 1 1 San Onofre 3 3 Brunswick 2 2 Limerick 2 2 Seabrook 1 1 Byron 1 1 Maine Yankee 2 Sequoyah 1 2 Byron 2 1 McGuire 1 2 Sequoyah 2 1 Callaway 1 1 McGuire 2 2 South Texas 1 1 Calvert Cliffs 1 3 Millstone 1 3 South Texas 2 1 .Calvert Cliffs 2 3 Millstone 2 3 St. Lucie 1 3 l 0 Catawba 1 2 Millstone 3 1 St. Lucle 2 2 Y Catawba 2 2 Monticello 2 Summer 1 1 Clinton 1 3 Nine MIIe Pt 1 3 Surry 1 3 Comanche Peak 1 1 Nine Mlle Pt 2 2 Surry 2 3 Cook 1 3 Nonh Anna 1 2 Susquehanna 1 1 Cook 2 3 Nonh Anna 2 2 Susquehanna 2 1 Cooper Station 3 Oconee 1 4 Three Mlle Island 1 3 Crystal River 3 3 Oconee 2 3 Trojan 3 Davis-Besse 1 3 Oconea 3 3 Turkey Pt 3 6 Diablo Canyon 1 1 Oyster Creek 1 4 Turkey Pt 4 6 Diablo Canyon 2 1 Palisat es 5 Vermont Yankee 1 3 t Dresden 2 4 Palo Verde 1 2 Vogtle 1 1 Dresden 3 4 Palo Varde 2 2 Vogtle 2 1 Duane Arnold 2 Palo Verde 3 2 Washington Nuclear 2 1 Farley 1 2 Peach Bottom 2 3 Waterford 3 2 Farley 2 1 Peach Bottom 3 3 Wolf Creek 1 1 Fermi 2 2 Perry 1 2 Yankee-Rowe 1 2 Fitzpatrick 3 Pilgrim 1 4 Zion 1 4 Ft Calhoun 1 3 Point Beat.h 1 3 Zion 2 3 Ginna 2 Point Beach 2 3 Grand Gulf 1 2 Table 3.1

l i Summary of Four Unimplemented USis [ 120 (111) (111) (111) (33o) i 100 ~ (80) i 80 - I (69) (s4) j g 80 -- (58) (g) l a__ j Y 1 20 -- l o 1 I i I j A-9 Anticipated ' A-44 Station A-46 Seismic A-47 Safety l Transients Without Blackout Qualification Of Equipment Irnplications of Scram in Operating Plants Control Systems i Legend E Applicable Plants ] Implemented Plants E Uni..4%; rented Plants Figure 3.2

hardware and procedure modifications. About 40 percent of the plants have already implemented procedure modifications, and it is expected that a large majority of licensees will complete implementation of the station blackout rule by the end of 1994. A 46 Seismic Qualification of Eaqipment in Ooeratina Plants The NRC staff has been reviewing the Generic implementation Procedure (GlP) developed by the Seismic Qualification Utility Group based on the experience database. The GIP is to be used for walkdown inspections to verify the seismic adequacy of equipment in those operating plants for the resolution of USI A-46. The Generic Safety Evaluation Report (GSER) on the GIP, Revision 0, was issued in July 1988. Supplemental Safety Evaluation Report (SSER) No.1 was issued in June 1990. After the issuance of SSER No. 2, each affected utility will be requested to submit its implementation schedule and to complete implementation within three years. A-47 Safety Imolications of Control Systems Westinghouse pressurized water reactors ('PWRs) have already implemented the modifications. Boiling water reactors (BWRs) and Combustion Engineering (CE) PWRs provided responses to the generic letter concluding that the modifications for the generic letter are not cost beneficial. NRR is preparing a CRGR review package that BWRs and CE PWRs should not be required to provide the system modification. Review of seven B&W plants is continuing. The B&W Owners Group has not proposed any relaxation since they do not yet have a position on this issue. 3.2 Verification Status For Generic iteres such as USIs, 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 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 l 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 prior to total implementation of all aspects of the issue's resolution by the licensee. Four 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 Ti2515/76 A 24 Oualification of Class 1E Safety Related Equipment Tl2515/85 A7 Mark I Long Term Program, NUREG 0661, Supplement 1 Additionally, verification of licensee implementation of the requirements of 10 CFR 50.63, which resolves USl A 44, Station Blackout, will be necessary A Tl is being developed for this purpose. All plants must be verified for compliance with station blackout requirements. Table 3.2 illustrates the items remaining to be verified for these five USis. Table 3.3 includes a summary of the verification status for each plant. Of the 429 items requiring NRC verification,288 items (67 percent) have been completed. ? 2 s I o

Summary of USI Items Requiring Verification Plants Plants Plants USI Covered Reauired Verified 24 23 A-7 Mark i Long-Term Program 24 110 87 l A-9 Anticipated Transient Without 331 g3 Scram ? A-24 Oualification of Class IE Safety-111 111 110 Related Equipment j t 73 68 A-26 Reactor Vessel Pressure Transient 74 Protection a 1i' O A-44 Station Blackout 111 NOTE-Covered Plants are those for which Usts are appEcable. Plants Required are those plarus requiring field verification. Plants covered but for wnich field venfication is not necessary have irnplemented i F the resolution in a manner not requiring plant hardware chariges. Table 3.2

1 3.3 Stalus by Plant Table 3.3 summarizes information on the status of implementation and verification of USIs at alllicensed 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. No plant has completed all applicable USIs. Twenty-five plants have completed Implementing actions for all except one of the applicable USIs. Four plants have six items remaining to be implemented and one plant has five items remaining to be implemented. The remaining 81 plants have two to four items remaining to be implemented. Five USIs require inspection to verify that implementing actions have been completed. One-hundred and seven plants have completed at least 50 percent of the applicable USIs requiring verification. For the remaining four plants, NRC verification is completc for one of the four USIs that are applicable at those plants. Appendix B lists the unimplemented USl items by issue and gives the projected implementation date, where applicable.. _.

f b i I l i e R-USI-001 l SAFETY ISSDE MANAGEMENT SYSTEM PAGE 1 i STATUS DF USI PLANTS - StDOWRY BY UNIT ___..___..___."TMENTAmW VERIMCAM ON 'f 2 ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PE R CENT UNIT APPLICA8tE. COMPLETED COMPLETED REMAINING COVERED REQUIRED .__....... COMPLETED COMPLETED l ARKANSAS 1 16 13 (81 3 4 4 3 - 75 l ' ARKANSAS 2 16 13 (81 3 4 4 3 75 BEAVER VALLEY'1 16 1* (87 2 4 4 3 75 l BEAVER VALLEY 2 15 14 {93 1 4 3 2 i SS BIG ROCK POINT 1 14 11 478 3 3 2 1 ' 59 BRAIDWOOO 1 15 14 i93 1 4 4 3 75 BRAIDWOOD 2-15 14 1 93 1 1 4 4 3 - 75 I 8ROWNS FERRY 1 18 12 66 1 6 4 4 2 1 50 '83 3 4 4 3 1 75 SROWNS FERRY.2 18 15 l SRDWNS FERRY 3 18 12 (66 5 4 4 2 1 50 I BRUNSWICK 1' -18 16 (88 i 2 4 4 3

75

- i ERUNSWICK 2 18 16 (88 1 2 4 4 3 1 75 i C) BYROM 1-16 15 1 93 1 1 4 4 3 1 75 e 8YRON 2 15 14 1 93 l 1 4 4 3 75 CALLAWAY 1 18 15

93 i

1 4 4 3 75 I i CALVERT CLIFFS 1_ 18 13 1 81-3 4 4 3 ' 75 CALVERT CLIFFS'2' 18 13 . 81 3 4 4 3

75 i

i CATAWBA 1, '18 14 ' 87 -2 4 4 3 1 75 f ' CATAWBA 2 18 14 l 87 2' 4 4 3 ' 75 .CLINTON 1 15-12 i 78 .3 3 3 2 SS COMANCHE PEAK 1 : .15. 14 i 83 1 4 4 3 ' 75 t ' COOK 1 17 14 i 82 3 4 4 3 1 75 - COOK 2 17 14' i 82 3 4 4 3 1 75 COOPER STATION-18-15 1 83 3 4 4 2 1 50 e i i CRYSTAL RIVE!! 3. 18 13 i 81 3 4 4 3 75 i + DAVIS-8 ESSE 1'. 10 13 i 81 i 3 4 4 3 1 75 DIABLO CANYON 1 18 15 93 1' 4 4 2 1 50 l 'DIABLO CANYON 2. 15- .14 93 1 4 4 3 1 75 t 'DRESDEN 2 ~ ~ 18 14

77

.4 4 4 3 l 75 i i i' DRESDEN 3 '18 16 1 88 t 2 4 4' 3 1 75 l 18 . 14 ' 1 77 4 4 '4 3 75 DUANE ARNOLD FARLEY 1 '18 14 1 87 2 4 4 3 1 75 t > FARLEY 2 18 15 '- 1 93' 'l 4 4 3 1 75 i FERM1 2 '16-14-l 87 2 -FITZPATRICK 18 15-l 83 4 4 3 1 75 t 4 4 3 i 75 1 FORT CALHOUN 1 16 .13 l 81 3-4 4 3 4 75 5 - GI NNA -... 16 le ! 87 2 4 4' 3 (75 ' I ' GRAND GULF'I-18 14 87-2 -3 3 2 (66 i i HADDAM NECK 18 15 ' i 83 3 4 4 3 (75 HARRIS 1 18 15 i 93. -1 4 14 3 (75 HATCH 1 18 15 1 83 1 3 4 4 3 i 75 i HATCH 2~ 18-14 ' 1 77 l 4 .4' 4 3 75 t i HOPE CREEK'l 17' -18 1 94 l 1-4 4 3

75 INDIAN POINT 2 18 14 1 87-2..

4 4 3 i 75 i i i i t Table-3.3 t z. ^- s m

R-USI-001 SAFETY ISSUE MANAGEMENT SYSTEM PAGE 2 STATUS OF USI PLANTS - SLH9ARY BY UNIT IMPLEMENTATION VERIFICATI0s ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS PE R CENT UNIT APPLICABLE COMPLETED COMPLETED REMAINING COVERED REQUIRED COMPLETED COMPLETED INDIAN POINT 3 16 13 181 9 3 4 4 3 175 KEWAUNEE 16 13 (81 3 4 4 3 1 75 i LASALLE 1 17 14 (82 1 3 3 3 2 1 66 LASALLE 2 16 13 (81 3 3 3 2 1 66 LIMEPICK 1 16 15 (93 l 1 3 3 2 < 66 LIMERICK 2 16 14 187 I 2 3 3 2 1 66 t MAINE YANKEE 16 14 i 87 2 4 4 2 1 50 t MCGUIRE 1 18 16 I 88 1 2 4 4 3 1 75 I PCGUIRE 2 18 16 1 88 ) 2 4 4 3 1 75 MILLSTONE 1 19 16 1 84 ) 3 4 4 3 1 75 l MILLSTONE 2 16 13 1 81 3 3 4 4 3 1 75 t i MILLSTONE 3 16 15

93 )

1 4 4 3 1 75 i MONTICELLO 18 1c 1 88 ) 2 4 4 3 i 75 i _a NINE MILE POINT 1 18 15 i 83 7 3 4 4 3 i 75 l e MINE MILE POINT 2 16 14 (8? l 2 3 3 2 - 66 NORTH ANNA 1 16 14 (37 2 4 4 2 l 50 NORTH ANNA 2 17 15 1R$ 2 4 4 2 - 50 OCONEE 1 16 12 1 75 4 4 4 1 1 25 0CONEE 2 16 13 1 81 2 4 4 1 1 25 'i OCONEE 3 16 13 l 41 l 3 4 4 1 1 25 ) OYSTER CREEK 1 18 14 177 4 4 4 3 i 75 t PALISADES 16 11 (68 1 5 4 4 3 (75 i PALO VERDE 1 15 13 ISS i 2 4 4 2 150 1 PALO VERDE 2 15 13 186 2 4 4 2 (50 1 PALO VERDE 3 15 13 86 2 4 4 2 (50 t i PEACH BOTTDM 2 18 15 1 83 3 4 4 3 (75 i PEACH BOTTDM 3 18 15 i 83 3 4 4 3 (75 3 PERRY 1 15 13 86 2 3 3 2 (66 i PILGRIM 1 18 14 i 77 4 4 4 .3 (75 POINT BEACH 1 16 13 31 1 3' 4 4 3 (75 i i POINT BEACH 2 11 13 (81 i 3 4 4 3 i75 i PRAIRIE ISLAND 1 46 14 i87 2 4 4 3 75 1 PRAIRIE ISLAND 2 16 14 i 87 2 4 4 3 75 t QUAD CITIES 1 18 14 - 77 4 4 4 3 ' 75 i QUA0 CITIES 2 18 14 1 77 4 4 4 3 1 75 i RIVER BEND 1 15 13 1 SS i 2 3 3 2 i 66 t ROBINSON 2 16 13 1 81 1 3 4 4 3 1 75 SALEM 1 '16 14 1 87 2 4 4 3 1 75 SALEM 2 17 15 . 88 2 4 4 3 1 75 l SAN ONOFRE 1 16 13 i 81 3 4 4 3 i 75 SAN ONOFRE 2 16 13 81 3 4 4 2 1 50 i i SAN ONOFRE 3 16 12 i 31 l 3 4 4 2 i 50 1 93 l 1 4 4 3 i 75 l SEA 9 ROOK 1 15 14 SEQUOYAH 1 18 16 I 88 t 2 4 4 2 (50 t Table 3.3

l t I r l i R-USI-001 SAFETY ISSUE MANA0EMENT SYSTEM PAGE 3 STATUS OF USI PLANTS - SUfetARY SY UNIT l .______........'. IMPLEMENTATION VERIFICATION _ _ _ = - - ITEMS ITEMS PER CENT ITEMS ITEMS ITEMS ITEMS Pest CENT i UNIT > APPLICABLE' COMPLEliD COMPLETES EEMAINING COVERED REQUIRED COMPLETED COMPLETED i . i SEQUOYAH 2 18 17 l 94 1 4 -4 2 1 5e i SOUTH TEXAS 1 15 14 ' 93 1 4 4 3 1 75 SOUTH TEXAS 2 15 14' 1 93 1 4 4 3 ( 75 ST LUCIE 1 16-13 1 81-3 4 4 2 1 50 I ST LUCIE 2-18 14 1 87 2 4 4 2 1 58 I supeER 'l .le 15 l 93 1 4 4 3 1 75 SURRY 1 18-13 1 31 3 4 4 2 1 50 SURRY 2 18 13 i 81 3 4 4 2 1 59 [ SUSQUEHANNA 1 17. 10 94 1 2 3 2 1 SS i i ' SUSQUEHAINGA 2 ' 18' 15 93 1 3 3 2 I es I i l THREE MILE ISLAND 1 'le 13 i 21 1 3 4 4 2 i se i TROJAN le 13 1 31 3 4 4 3 1 75 t TURKEY POINT 3 18 10 ' i 52 8 4 4 2 i 50 t i , TURKEY POINT 4' is-10 i 82 8 4 4 2 i so I VERMONT YANKEE 1 18 15 I 83 3 4 4 3 1 75 .g YOGTLE 1 15 14 1 93 1 4 4 2 1 50 2 l V0GTLE 2 18 15 l 93 1 4 4 1 i 25 m 'itASHIIIGTON NUCLEAR 2-. 11e if i 93 1 3' .3 2 i ss e - idATERFORD 3-15 ' 13 1 SS 2 4 4 3 L75 i WOLF CREEK 1 '18 - 15 l 93 1 4 4 3 1 75 YANNEE-ROWE 1 le 14 i 37 2 4 4 3 i 75 ZION 1. is 12 1 75 4 4 4 3 1 75 ZION 2 19 13 I 81 3 4 4: 3 1 75 J 1 TOTALS / AVERAGES 1819 1545 SS 274 431 429 288 87 i k i k i Table 3.3 i ?

3.4 Status by issua Table 3.4 presents summary information on the status of implementation and verification of each USI. For each issue, the table shows the number of applicable plants, the number and percentaDe of plants that have completed implementation, and the number of plants remaining to complete implementation. For those issues requiring NRC verification of corrective ections, 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 27 USis,13 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.) Four USts account for 91 percent of the unimplemented items: A 9, Anticipated Transient Without Scram, with 23 plants remaining to complete implementation; A 44, Station Blackout, with 110 plants remaining to complete implementation; A 46, Seismic Qualification of Equipment in Operating Plants, with 64 plants remaining to complete implementation; and A 47, Safety implication of Control Systems, with 53 plants remaining to complete imolementation. These inur, largely unimplemented, USIs are in varying stages of NRC review and licensee implementation, as discussed in Section 3.1 of this report. Ten plants have not implemented corrective actions for USl A 48, Hydrogen Control Measures and Effects l of Hydrogen Burns. The remaining USis have from one to three plants remaining to complete implementation. NRC inspection to verify licensee implementation is required for five USIs; verification is not complete for any of these USIs. Two USis - Anticipated Transients Without Scram (ATWS) and Station Blackout - account for 134 of the 141 outstanding verifications. Station blackout measures have been implemented at only 1 of the 111 applicable plants and, therefore, cannot be verified at this time at most plants. t I I r 6 a i t R-USI-002 l SAFETV ISSUE MANAGEMENY SYSTEM PAGE 1 l t STATUS OF USI PLANTS - SUpetARY BY ITEM l f IMPLDENTATION VERIFICATION PLANTS PLANTS PER CENT PLANTS PLANTS PLANTS PLAerTS PER CENT b ITEM APPLICA8LE COMPLETED COMPLETED REMAINING REQUIRED C0vtRED REQUIRED COMPLETED COMPLETED ? t A-1 111 111 (1001 WATER HApeER ~0 NO r A-2 74 74 (100) 0 NO ASYpetETRIC 8 LOWDOWN LOADS ON REACTOR PRIMARY C00LANT SYSTEMS A-3,' 4 AND S 74-74 '(1003 0 NO STEAM GENERATOR TUBE INTEGRITY .A-6 23 23 '(100) 0 NO i MARK I SHORT-TERM PROGRAM A-7 24 22 (91 1 2 YES 24 24 23 (95 ) I i MARK 1 LONG-TERM PROGRAM 2n Ab A-8 5 S (1001 0 NO F othWK II CONTAINMENT POOL DYNAMIC LOADS LONG-TERM PROGRAM I ' A-9 111 88 (79 1 23 YES 111 110 87 (79.3 h ATWS A-10 36 35' (97 ) 1 NO - i BWR FEEDWATER N0ZZLE CRACKING L A. 111 108 (97 ) 3 NJ REACTOR VESSEL MATERIALS TOUGHNESS ? 'A-17 111 til : (100) 0 NO SYSTEM INTERACTIONS IN NUCLEAR. POWER PLAsiTS A-24 111 109 (98 ) 2 YES 111 111 110 - 199 ) I QUALIFICATION OF CLASS IE SAFETY-RELATED EQUIPMENT ) A-26 . 74 74 (100j 0 YES 74 73 68 (93 ) l REACTOR VESSEL PRESSURE TRANSIENT PROTECTION i A-31 50 48-(97 3 1 NO { RHR SHOTDOWN REQUIREMENTS A-36 (C010) 11'l 108 (97 ) 3 NO CONTROL OF HEAVT LOADS OVER SPENT FUEL POOL (PHASE ONE) A-36 (C015) 79 - 79 (2001 0 No i .i l CONTROL OF HEAVY LOADS - PHASE II (FOLLOWUP OF,MPA8 C-10) i i -} Table 3.4 j

e f R-USI-002 SAFE 7Y ISSUE MANAGEMENT SYSTEM PACE 2 h STATUS OF USI PLANTS - SUPMARY BY ITEM I IMPLEM NTATION VERIFICATIDet i PLANTS PLANTS PER CENT PL.MNTS PLANTS PLANTS PLANTS PER CE NT ITEM APPLICABLE COMPLETED COMPLEIED REPRINIhG REQUIRED COVERED REQUIRED COMPLETED COMPLETED A-39 36 36 (100] O NO I DETERMINATION OF SRV POOL OVNAMIC LOADS & TEMP, LIMITS FOR BWR CNTMNTS I cA-40 3 3 (1001 0 NO SEISMIC DESIGN CRITERIA A-42 38 38 (100l 0 NO ! PIPE CRACKS IN BOILING 1 DATER REACTORS 3 4-43 111 111' (100) 0 WO CONTAINENT [ERGENCY SUMP PREFORMANCE l A-44 111 1 [0 ) 110 YES 111 111 9 to 3 STATION BLACKOUT h A-45 '111 til' (200) 0

1. 0 Ln SHUTDOWN DECAY HEAT REMOVAL REQUIREMENTS A-es es 5

(7 1 44 No SEISMIC QUALIFICATIDW 0F EQUIP 9ENT IN OPERATING PLANTS 1 A-47 111 . Se . (52 ) 53 No SAFETY IMPLICATIDW OF CONTROL SYSTEFS-A-43 47 37 178 3 10 NO HYDROGEN CONTROL 8CASURES AND EFFECTS OF NtDROGEN SURNS A-49 '74 72 (ST ) 2 NO 'i PRESSURIZED THERMAL SHOCK t c t i t Table 3.4 i i t .._y-

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 followir.]: The NRC closure process for USls ensures continued adequate protection of the public health and safety. All USIs have been resolved by the NRC, and significant progress has been made in implementing and verifying required changes at plants. Licensees are making adequate progress toward implementing requirements imposed following the NRC's resolution of USIs, and the framework exists to oversee future implementation of delayed items. Although the resolution of USls involves complex technical issues and analyses, it appears that all required implementation items can be completed in accordance with regulatory requirements. l

_= 4 GENERIC SAFETY ISSUES This section presents the overall status of implementation and verification of generic safety issues (GSI) applicable at the 111 licensed nuclear power plants. Because each GSI may be tracked 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 to meet the requested actions at licensed plants. The information presented here includes all GSI items related to the 111 plants considered in this report. Approximately 86 percent of the GSI items have been implemented at licensed plants. Of the 2,673 items,2,283 have been completed and 390 remain open from an implementation standpoint, On average, nach plant has less than 4 items to implement, and no plant has more than 9 remaining items. Figure 4.1 presents the overall status of, and progress on, GSis. Of the 111 plants,3 have implemented all applicable GSis. Table 4.2 lists the number of unimplemented items by unit. Appendix C lists the unimplemented GSI items by issue and gives projected implementation dates. Seven GS!s have not been implemented at a significant number of plants for which they are applicable; these account for approximately 95 percent of the unimplemented items. Figure 4,2 summarizes the implementation status of these issues. A brief description of each issue follows. GSI 43 Reliability of Air Systems This issue arose from concerns related to the TMI accident and air-operated equipment failures at other plants, in August 1988, the staff issued Generic Letter 88-14 to specify the performance of a design and operations verification of instrument air systems and descriptions of licensees' programs for maintaining proper instrument air quality. The staff gave licensees six months in which to confirm that these actions had been accomplished or to commit to perform them during a subsequent outage. The licensees for about 74 percent of those plants that still have this issue open are scheduled to complete implementation by the end of 1992. 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 -4 9-

GSI Numbers and Corresponding SIMS Item Numbers MPA SIMS GSINo. _HE Item No. SIMS Title 40 B-065 40 Safety Concems Associated With Ppe Breaks in BWR Scram System 41 B-050 41 BWR Scram Discharge Volume Systems 43 B-107 GL-88-14 Instrument Air Supply System Problems Affecting Safety-Related Equp. 51 L-913 GL-89-13 Service Water System Problems Affecting Safety-Related Equipment 67.3.3 A-017 67.3.3 Improved Accident Monitoring 70 B-114 70 PORV and Block Valve Reliabihty 75, item 1.1 B-076 75 (8076) ttem 1.1 - Post-Trip Review; Program Description & Procedures 75, item 1.2 B-085. 75 (8085). Item 1.2 - Salem ATWS 1.2 Data Capabihty 75, item 2.1 B-077 75 (8077) Item 2.1 - Equipment Classification & Vendor interface - RTS Component 75, item 2.2.1 B-086 75 (8086) Item 22.1 - Salem ATWS 22 S-R Components 75, item 2.2.2 L-003 GL-90-03 Item 22.2 - Relaxation of Stat! Pos in Gen Letter 83-28, item 22 Part 2 75, items 3.1.1 & 3.1.2 B-078 75 (B078) liems 3.1.1 & 3.1.2 - Post-Maintenance Test Procedures & Vendor Recomm. 75, item 3.1.3 B-079 75 (B079) Item 3.1.3 - Post-Maintenance Testing - Changes to Tech Specs - RTS Component 75, items 32.1 & 32.2 B-087 75 (8087) Items 32.1 & 3.22 - Salem ATWS 32.1 & 32.2 S-R Components 75, item 3.2.3. B-088 75 (B088) !!em 32.3 - Salem ATWS 3.2.3 T.S. S-R Components) .8

75. Item 4.1 B-080 75 (8080)

Item 4.1 - Reactor Trip System Reliability - Vendor Related Mods

75. Items 4.2.1 & 42.2 B-081 75 (8081) ftems 4.2.1 & 422 - Prevertative Maint Prog for Reactor Trip Breakers 75, item 4.3 B-082 75 (8082)

!! era 4.3 - Autornatic Actuation of Shunt Trip Attach. for West & B&W 75, item 4.3 B-090 75 (B090) Item 4.3 - Salem ATWS 4.3 W and B&W T.S. 75, item 4.4 B-091 75 (B091) !!em 4.4 - SaMm ATWS 4.4 B&W Test Procedt.res 75, Item 4.5.1 B-092 75 (8092) ftem 45.1 - Salem ATWS 4.5.1 Diverse Trip Features 75, items 4.5.2 & 4.5.3 B-093 76 (8093) items 4.52 & 4.5.3 - Salem ATWS 4.52 & 4.5.3 Test A!!ematives 86 B-084 86 Long Range Plan Dealing With Stress Corrosion Cracking in BWR Piping 93 B-098 GL-88-03 Resolution of GSI 93," Steam Binding of Auxiliary Feedwater Pumps-94 B-115 94 Additional Low-Temp Overpressure Protection for LWRs 99 L-817 GL-88-17 Loss of Decay Heat Removal 124 S-001 124 Auxiliary Feedwater System Reliability A-13 ?-107 GL-80-099 Tecimical Specification Revision for Snubber Surveittance A-13 B-022 GL-84-13 Technical Specification for Snubbers A-16 D-012 A-16 Steam Effects on BWR Core Spray Distribution A-35 B-023 MPA-B023 Degraded GrkiVoltage B-10 S-008 B-10 Behavior of BWR Mark 111 Containments B-36 none B-36 Dev Design. Test & Maint Criteria for Atmo Cleanup Sys Air Finer & Adsorption Units B-63 B-045 GL-80-011 LWR Primary Coolart System Pressure isolation Valves Table 4.1

1 \\ Generic Safety issues In:plementation Status at Licensed Plants 3000 2500 2000 2 1500 -- p 2673 2283 H 1000 o Applicable implemented Unimplemented Figure 4.1, --w n m e-.ee -->w-

Summary of Unimolemented GSI Items by Pfarit items Items items PLANT Remaining PLANT Remaining PLANT Remaining Arkans8s 1 2 Haddam Neck 6 Prairie Island 1 4 Arkansas 2 3 Harris 1 3 Prairie Island 2 4 Beaver Valley 1 5 Hatch 1 2 Quad Cities 1 3 Beaver Valley 2 4 Hatch 2 2 Quad Cities 2 4 i Big Rock Pt 1 1 Hope Creek 1 2 River Bend 1 2 Braidwood 1 4 Indian Pt 2 4 Hobinson 2 2 Braldwood 2 5 Indian Pt 3 5 Salem 1 4 Browns Ferry 1 6 Kewaunee 4 Salem 2 4 Browns Ferry 2 3 LaSalle 1 2 San Onotre 1 9 Browns Ferry 3 7 LaSalle 2 3 San Onofre 2 5 Brunswick 1 1 Limerick 1 1 San Onofre 3 5 Brunswick 2 2 Limerick 2 1 Seabrook 1 5 Byron 1 6 Maine Yankee 3 Sequoyah 1 2 Byron 2 5 McGuire 1 6 Sequoyah 2 2 Ca!!away 1 2 McGuire 2 6 South Texas 1 4 Calvert Cliffs 1 5 Millstcne 1 4 South Texas 2 4 Calvert Cliffs 2 5 Millstone 2 4 St. Lucie 1 4 Catawba 1 6 Millstone 3 4 St. Lucie 2 4 Catawba 2 6 Monticello 1 Summer 1 4 Clinton 1 3 Nine Mlle Pt 1 3 Surry 1 3 Comanche Peak 1 3 Nine Mlle Pt 2 4 Surry 2 4 Cook 1 4 Nodh Anna 1 3 Susquehanna 1 1 Cook 2 4 Nodh Anna 2 3 Susquehanna 2 1 Cooper Station 2 Oconee 1 4 Three Mile Island 1 2 Crystal River 3 5 Oconee 2 5 Trojan 5 Davis-Besse 1 3 Oconee 3 3 Turkey Pt 3 5 Diablo Canyon 1 4 Oyster Creek 1 0 Turkey Pt 4 5 Diablo Canyon 2 4 Palisades 4 Vogtle 1 4 Dresden 2 3 Palo Verde 1 4 Vogtle 2 4 Dresden 3 4 Palo Vorde 2 4 Waterford 3 2 Farley 1 3 Palo Verde 3 3 Wolf Creek 1 3 Farley 2 3 Peach Bottom 2 3 Yankee-Rowe 1 3 Fermi 2 1 Peach Bottom.3 3 Zion 1 7 Fitzpatrick 3 Perry 1 2 Zion 2 7 Ft Calhoun 1 4 Pilgrim 1 2 Ginna 4 Point Beach 1 3 Grand Gulf 1 2 Point Beach 2 3 Table 4.2

j Summary of Seven Unimplemented GSis j 7 1 i I (iii) (111). (111) (iii) i 100 f f (84) (83) (82) 80 3 g4) (se) i (67) (67) i,- m 60 i ~ 5 (0) 43 51-67.3.3 70 75(2.2.2) 94 99-I GSI Numbers Legend Total lii-;:zin." 2 Figure 4.2 4 Unimplemented

GSI 51 Proposed ReqVkfments for Imoroving the Reliability of Ooen-Cyrig Service Water Systems 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 Generic Letter 8913 requesting licensees to take certain actions and establish programs to 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. Because the request is so recent, licensees have not yet implemented the actions and programs at most plants. About 90 percent of all plants are scheduled to complete implementation of this issue by the end of 1992. The staff considers the status of th GSI acceptable. GSI 67.3.3 Imoroved Accident Monitorina This issue addresses conformance with Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident.' The staff issued Generic Letter 82 33 in December 1982 to request schedules and details of the licensees' plans to implement the provisions of Regulatory Guide 1.97, Revision 2. Based on responses to this generic letter, the staff issued confirmatory orders in 1985. Because the industry has taken exvption to and appealed some of the provisions of Regulatory Guide 1.97, Revision 2, implementation is incomplete at many plants. Most boiling water reactors (BWRs) have not installed the Category 1 neutron flux monitoring system. Many pressurized water reactors (PWRs) have not installed Category 2 qualified instrumentation to monitor accumulator tank level and pressure and containment sump temperature. The staff is reevaluating these - positions for both BWRs and PWRs and is preparing a new generic letter that will relieve and/or clarify these provisions cf the guide, GSI 75 Utem 2.2.2) Vendor Interface for Safetv-Related Comoonents This issue addresses several Anticipated Transient Without Scram (ATWS) items. In March 1990, the staff issued Generic Letter 90 03 as revised guidance. addressing GSI 75, Salem ATWS item 2.2.2. Generic Letter 90 03 supersedes the original guidance on this item issued in Generic Letter 83 28. Industry responses to Generic Letter 90-03 were due by the end of September 1990. Allindustry' responses have been received, As a result of Generic Letter 90-03, many licensees are revising their vendor interface program, Subsequently, there are a.. number of licensees that have not completed implementation. GSI 99 Reactor Coolant System / Residual Heat'Removat Suction Line Valve Interlock on PWRs This issue correrns inadvertent closing of residual heat removal (RHR) suction. valves when the RHR system is in use, especially during mid-loop operation, resulting in possible loss of decay heat removal capability. Generic Letter 88-17, 54-

\\ issued in October 1988, superseded and closed out an earlier generic letter of more limited scope and was intended to improve industry's understanding of the significance of such events. As recommended in Generic Letter 8817, several expeditious actions have been completed at all plants, in addition, Generic Letter 8817 requested plans and schedules for implementation of a number of Mnsa term program enhancements to be completed by specified subsequent refwling outages. Essentially all of those plants that still have this issue open are scheduled to complete implementation by the end of 1992 in accordance with the generic letter. Tha staff considers this acceptable. GSI 70 PORV and Block Valve Reliability, and GSI 94 Additional Low-Temperature Overoressure Protection for Llaht Water B9E1QLS The issuance of staff positions resulting from the resolution of GSI 70 and GSI 94 is relatively recent. As a result very few plants have implemented GSI 70, and no plants have implemented Gli 94. Generic Letter 90-06, which presented the staff position resulting from the resolution of these two GSis was issued to licensees on June 25,1990, to be implemented by the end of the first refueling outage, beginning six months or later from the date of the generic letter. 4.2 Verification Status For generic items such as GSis, the Office of Nuclear Reactor Regulation issues temporary instructions (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 TI, 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 1,091 items requiring NRC verification, 1,008 (92 percent) have been completed. Seven 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. __ t Temporary Instructions k t ' esolved GSis SIMS Item .WMS Titto _TJ 41 BWR SCRAM DISCHARGE VOLUME SYSTEM 2515/090 ) 67.3.3 IMPROVED ACCIDENT MONITORING 2515/087 75 (B077) ITEM 2.1 EQUIPMENT CLASStFICATION & 2515/064 VENDOR INTERFACE RTS COMPONENT 75 (B078) ITEMS 3.1.1 & 3.1.2 - POST MAINTENANCE TEST 2515/064 PROCEDURES & VENDOR RECOMM, 75 (B079) ITEMS 3.1,3 - POST MAINTENANCE TESTING - 2515/064 CHANGES TO TECH SPECS RTS COMPONENT 75 (8080) ITEM 3.1 REACTOR TRIP SYSTEM RELIABILITY. 2515/091 VENDOR RELATED MODS 75 (8081) (TEMS 4.2.1 & 4.2.2 - PREVENTIVE 2515/064 MAINTENANCE PROGHAM-FOR REACTOR TRIP BREAKERS - SALEM ATWS 3.2.1 & 3.2.2 S-R COMPONENTS 75 (8096) 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 (8088) SALEM ATWB 5.2.3 T.S. S-R COMPONLNTS 2515/064 75 (8092) SALEM ATWS 4.5.1 DIVERSE TRIP FEATURES -2515/064 I 88 LONG RANGE PLAN DEALING WITH STRESS 2515/089 CORRC<SION CRACKING IN BWR PIPING GL-88-17 1.OSS OF DECAY HEAT REMOVAL 2515/101 2515/103 Table 4.3 i 56- .n A

Summary of GSI Items Requiring Verification Plants P!snts Picnts SIMS. Item l Covered Recu! red Vertfled 41 BWR SCRAM DISCHARGE VOLUME SYSTEMS 37 37 36 67.3.3 IMPROVED ACCIDENT MONITORING 111 110 85 75(0077) ITEM 2.1 - EQUIPMENT CLASStFICATION & 111 98 95 VENDOR INTERFACE - RTS COMPONENT 75 (6078) ITEMS 3.1.1 & 3.12 -POST MAINTENANCE 111 99 96 TEST PROCEDURES & VENDOR RECOMM. 75 (B079) 1 TEM 3.1.3 - POST MAINTENANCE TESTING - 111 93 95 CHANGESTO TECH SPECS - RTS COMPONENT 75(8080) ITEM 4.1 - REACTOR TRIP SYSTEM 74 74 72 RELIABILITY-VENDOR RELATED MODS 75(8081) ITEMS 42.1 & 422 -PREVENTATIVE MAINT 74 68 68 PROG FOR REACTOR TRIP BREAKERS g N 75 (8086) SALEM ATWB 22 S-R COMPONENTS 111 99 95 75 (8087) SALEM ATWS 32.1 & 32 ? C-R COMPONENTS 111 99 98 75(8088) SALEM ATWS 32.3 T.S. S-R COMPONENTS 111 99 95 75 (B092) SALEM ATWS 45.1 DIVERSF TRIP FEATURES 111 39 98 86 LONG RANGE PLAN DEALING WITH STRESS 36 36 34 CORROSION CR/sXING INBWR P! PING GL-88-1'! - LOSS OF DECAY HEAT REMOVAL 74 74 41 NOTE:. Plants C:- c sd are those for wNch GSis are appleable Plants Required aro those plants requirit:g field verification. Plants covered but hw which field verffication is act necessary have implemented the resolution in a mse:nor not requiring plant 7:ardware changes. Table 4.4

4.3 .Sletus by Plant Table 4.5 summarizes the status of implementation and verification of GSis at all licensed plants For each pant, 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 GSIs that require NRC to verify implementation of j corrective actions, the table shows the number of items covered by the Tis at each plant, the number of iterts requiring verification, and the number and percentage of items completed. Appendix C lists the unimpleme-ted GSI items by issue and gives projected imp;ementation dates. 1 Of the 111 plants,3 have completely implemented all GSI ltems; 25 plants have completed implementation actions for all except one or two GSIs; 72 plants have three to five items to implernent. The remaining 11 plants have fewer than nine items to implement. All of the items requiring verification by inspection (in accordance with a - TI) have been completed at 50 plants. Another 57 plants have completed at least two-thirds of the applicable items requiring such verification.~ l L l.-

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i 4.4 Status byjgsue 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, the number and percenta00 of plants that have completed implementation, and the number of p%nts remalrMg to complete Implementation. For those issues requiring verification of corrective totions, the table shows the number of plants covered by a TI, the nurther of plants requiring verification, and the number and percentage of plants that hevo compmted verification. Of the 34 GSis and sub Issues,17 have been fully implemented. Five issues remain to be implemented at only one plant each and five more issues remain to be Implementeo at two to four plants each. The seven issues discussed in Section 4.1 of this report account for 372 (95 percent) of the 390 items remaining to be implemented. l I Y 63- ~...

R-CSI-ee2 g,7gyy 33syg MAmAGEMEaT SY$ TEM P"8E 3 STATUS OF GSI PLAmTS - SUPO444Y SY ITEM IMPLE8ENTATIOm vtEIFICAT10m = _ _ PtamTS PLANTS Pte CENT PLANTS PtAmts PtANTS PtAmTS PER CEmi ITEM APPLICA8LE COMPLETED CDMPLETED REMAIsluG REQtJIRED COVERED

1. E9EIRED CasuPt.ETED CauqPLE TED 40 33 38 (93 1 2

NO SAFETY ConCERWS ASSOCIATED WITM PIPE GREARS Im Swt SCRAM SYSTEM 4: 37 3e ts7 1 1 YES 37 37 3e (37 3 swa ScaAM DISCMAmet v0 List STSTEMS 67 3.3 111 37 133 1 74 Yt3 til 11e as (T7 3 IMPROVED ACCIDENT MONITORING .To se a is 3 se no Poav Amo sLOCK valve RELIAeILITY 75 (sers) 111. 121 floal e me ITEM 1.1 - POST TRIP REVIEW; PROGRAM DESCRIPTICm & P*0CEDURES d) 75 1s0773 tin st1 aseen o YES 111 es 35 ges 3 p ITEM 2.1 - EQUIPMENT CLASSIFICATI0m & VEmDOR INTERFACE - RTS COMP 0asENT 75 (9078) 111 ItI (100) S YES 111 pg og gpg g ITEMS 3.1.1 & 3.1.2.-PCST MAINTENAssCi TEST PROCEDURES & VENDOR RECCoot. 75 (8079) 111 111 11003 e VES 111 39 35 ges 3 ITEM 3.1.3 - POST MAINTEmamCE TESTING - CHAssGES TO TECet SPECS - RTS CD 7s (8089] 74 '74 (100) 0 YES 74 74 72 (37 3 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VE8E)OR RELATED MODS 7s (8481) 74 72 (97 1 2 YES 74 es et (2003 ITEMS 4.2.1 & 4.2.7 -PREVENTATIVE MAINT PROG FOR REACTOR TRIP SWtARERS rs toes 7: se se troot o =0 " ITEM 4.3 - AUTOMETIC ACTUATIost OF SMUmT TRIP ATTM:H. FOR WEST & S&W 75 teoss 1:1 te7 tes 4 to SALEM ATwS 1.2 DATA CAPAeILITY 7s teess sal 111 gloss o vES 111 se es t.s SALEM ATwS 2.2 S-E COMPONENTS 7s 19057) lit 111 (100) 9 YES 111 SS Se 194 3 SALEM ATWS 3.2.1 & 3.2.2 5-R COMPonE375 7s tsees all 111 gloos o YES 111 es ss tes SALEM ATwS 3.2.3 T.S. S-A COMPONENTS Table 4.6

t I i l i i L i i I [ R-GSI-ee2 f. 3AFETY ISSUE MAMAGEMENT SYSTEM PaeE 2 a i, f STATUS OF GSI PLANTS - 54pemRY SY ITEM { i-IMPLEMNTATION WERITICATISW i i PLANTS PLANTS PE R CENT PLANTS PLANTS PLAftTS PLANTS PE R CENT [ ITEM APPLICABLE COMPLETED CONPLETED REMAINING REQUIRED COVERED REQUIRED CsMPLETED COMPLETED 75 (8 9 1 $s $s les 3 3 NO L -SAL.EM ATwS 4.3 W Aes SaW T.S. j 75 t90e11 '7 8 Ie5 3 I 98 0 l

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SALEM ATw$ 4.4 saw TEST PROCEDURES j 1 75 18e923-111 111' (1901 0 YES III to 33 (ss 3 SALEM ATwS 4.5.1 DEVERSE TRIP I'EATURES 75 (39 31 111 to9 (ss 1 2 NO r 4 SALEM ATwS 4.5.2 & 4.5.3 TEST ALTERNAT1vts l se 3e 3e itsel e YES 3e ts 34 (34 3 ). i .C) LONG RANGE PLAel DEALING WITM STRESS Co##0$ iou CRACKING I4 BWR PIPING Ur se s7 e-to i si No i !r ADDITIONAL LOW-TEMP. DVERPRESStJRE PROTECTION FOR LWes i I 124 8 5 (83 1 1 m0 AUXILIARY FEEDWATER SYSTEM RELIABILITY l A-16 2 2 (Ecol e NO STEAM EFFECTS ON SWR CORE SPRAY DISTRIBUT!Oei I I s-to 4 4 treel e me. i SEMAVIOR OF SWR MARK III CONTAIngENTS r 4 3-36 2e 28 (1se] e NO { DEV DESIGII. TEST & 8 MINT CRITERIA FOR ATM CLEANUP SYS AIN FILTER & ADSO GL-se-e14 les Iss tes 1 I m0 t LWR PRIMARY COGLANT SYSTEM PRESSURE ISOLATI0sl WALVES i st-se-ese 1s2 ter (1een e =0 TECHNICAL SPECIFICATI0m RFv1SION FOR SNUSSER SURVEILLANCE j { sess.12 s7 er tace) e NO TECM41 CAL SPECIFICATI0st FOR SepJesERS i OL-se-14 111 se 175 77 NO INSTRUMENT AIR SUPPLY SYSTEM PRestEMS AFFECTING SAFLTY-s]rELATED EQUIPM [ ? et.ss.e3 T4 T4 steet e no j . RESOLUTION OF GEIERIC SAFETY ISSWE 93,

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• LAufS PE R CE NT ITEM APPLICABLE COMPLETED COM*LETED REMAINING PEQUIRED COVERED REQUIRED COMPLETED COMPLETED GL-38-17 74 44 (58 )

30 TES 74 74 41 ($$ $ LOSS OF DECAY HEAT REMOVAL Gt-ss-13 111 29 (26 ) 82 no SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EQUIP 9(NT GL-90-03 111 83 174 1 28 NC RELAXATIO4 0F STAFF POS IN GEF LETTER 83-2F. ITEM 2.2 PART 2 MPA-8073 111 105 (97 1 3 40 DEGRADED GRID VOLTAGE .c) m. Table 4.6

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 adequate to protect the public health and safety. Licensees are making significant progress toward implementing GSI related actions requested by the staff, and the framework exists to oversee future implementation of delayed items. Slgnificant progress has been made in verifying the completion of implementation actions associated with those GSIs that have been resolved, The overall status of the seven largely unimplemented GSIs is generally acceptable because of the relatively recent issua'nce of staff positions on three of the GSis, and projected implementation schedules for the remaining four The NRC staff is preparing a new generic letter to revise Regulatory Guids 1.97, Revision 2, to modify and/or clarify certain provisions of this guide relating to the implementation of GSI 67.3.3, Improved Accident Monitoring. 67

i Appendix A LISTING OF UNIMPLEMENTED TMI ITEMS BYISSUE I . ~.,

APPENDIX A This appendix provides a detailed list, by issue, of the 123 TM) Action Plan items not implemented, along with the projected target date for completing the item. Status and projected implementation datos are presented as of September 30,1991. I -A1

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• L L t L L tL L E E ( e

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• F F f P r r P rp P F P rP P P s P P s P r P P r p o0 0 a aa m

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• • (32*2 sto test r=M - omtaFICatice or ses aCCLovulators (4/t3

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ApponF B LISTING OF UNIMPLEMENTED USl ITEMS BYISSUE t

APPENDIX B This appendix provides a detailed list, by issue, of the 274 U31 items not implemented, along with the projected date for completing the item. Statur, and projected implementation dates are presented as of September 30,1991 B 1-i

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tart Catt ISSUE

• tPa Ptadt tac TIttE 05/53 36.

a-44 4022 DavtS-BESSE

• e68536 Staitcus Stacrotit c3/93 37 a-M a022 ptaRo Craton 1 se68537 Staiten stacrovt 38.

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h ,i i ? 'I J Appendix C i P L LISTING OF UNiMPLEMENTED GSl ITEMS BYISSUE a ? E b 9 k .i i + t 1 l l 4 k F 6 c s ? e ---w.m-rwe,--+-* u 2 y 4.m- -w +.*e-r ,w w m y-vy -r w w v.,y, -w w ,,rv,,e,4, + -. -,-,,v-- -,,,w-,-e<,~ .c y,,wy,,,,m,n., y wy %,,r-v -t w y* -r-w+.. .--v=y=e-+yy

APPENDIX C This appendix provides a detailed list, by issue, of the 390 GSI items not implemented, along with the projected date for completing the item. Status and projected implement"ation dates are presented as of September 30,1991. ~ ? h C1

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EWL LATE ISSUE MPA PLANT TAC fifLE 211. 94 8115 TURKEY POIki 3 MT7464 AD0litDNAL LOW-TEMP. OVERPRESSURE PROTECTION FOR LWt$ 12/92 412. 94 8115 TURrEY Poluf 4 M77465 ADDITIONAL LOW-TEMP. OVERPRESSURE peofECTrom Fce tWr$ 12/92 213. 94 8115 v0 Gile 1 M77466 ADDITIONAL LOW-TEMP. OVERPRES1URE PROTECTIOu FOR lwr $ 03/92 214. 94 8115 v0GTLE 2 MT7467 ADDIflohAL LOW-TEMP. OVERPRESSURE P90fECTIOu FOR LWR $ 03/92 215. 94 8115 WATERFORD 3 MTT468 A00filonAL LOW-TEMP. OVERPRESSURE Pe0TECTIon FOR LWt1 0=/93 216. 94 8115 WOLF CREEE M77471 ADDITIONAL LOW-TEMP. OVERPRESSURE PROTECitou FOR LWR $ 03/92 217. 94 8115 YANKEE ROWE 1877472 ADDIT!Omat LOW-TEMP. OVERPPESSURE PROTECTfon FOR LWRS / 218. 94 8115 ZION 1 M77473 ADDITIONAL LOW-TEMP, DVERPfES$Uff PROTECTION FOR LWRf / 219. 94 8115 ZION 2 MT7474 ADDITIONAL t0W TEMP. OVERPRESSURE P#0TECitom FOR tw$ / 220. GL-80-014 8045 - NADDAM WECK M12916 LWR PelMARY C00LAuf SYSTEM PRES $U#E ISOLAi!CEE V4lvfS 12/91 221. GL-88-14 8107 8EAVER VALLEY 1 M71624 ' twSTRtp4ENT AIR SUPPtf SYSTEM PR08tEMS AFFECTimG SAFEff-ettATED EcutPM 02/93 i 222. GL 88-14 8107 BROW 4S FERRY 1 M71611 - INST #UMENT AIR SUPPLT SYSTEM PR08tEMS AFFECituG SAFETY-RELATED EQUtm 01/96 h 223. GL-88-14 8107 880WNS FEPRT 3 W71633 INSteumENT AIR SUPPLY SYSTEM Pe08tEMS AFFEC11mG SAFEff-RELATED Ecutm 06/93 ED 224. GL-88-14 8107 CATAWBA 1 M71641'. INSitUMENT Att SUPPtf SYSTEM P908tEMS AFFECilNG SAFEff-# ELATED EgbepM 06/93 225. -GL 88-14 8107 CATAWBA'2 l' M71642 INSTRUMENT AIR SUPPLY SYSTEM P908tEMS AFFECTING SAFEff-RELATED E001PM %/93 226. GL-88-14 8107 CtINTON 1 M71643 InSTRtp4ENT AIR SUPPtY SYSTEM PROBLEMS AFFECilhG SAFETY-RELATED EQUIPM 12/91 ) 227. GL-88-14 8107-DRESDEN 2 M71653 InSTRUFENT AIR SUPPtY SYSTEM PROBLEMS AFFECTING SAFETY-RELATED foutm 12/92 j

l 228.

GL-88-14 8107 DRESO u 3 M71654 INS 79'JMENT AIR SUPPtf SYSTEM PROBLcMS AFFECTimG SAFETY-RELATED Eculm. 12/92 d 1 229. GL-88-14 8107 FIT 2PATR1 E M71660 IsSTRUMENT AIR SUPPtY SYSTEM PRCSLEMS AFFECTING SAFEff-eELATED E001PM 83/92 230. GL-88-14 ' 8107 MCGUIRE 1 M71679 14STPJMENT Alt SUPPtf SYSTEM PR08tEMS AFFECTING SAFETT-RELATED Ecu1PM 12/91 231. GL-88-14 8107 MCoutRE 2 M71680 INSirJMENT air SUPPtf SYSTEM PR08tEMS AFFECTING SAFEff-RELATED Ecu1PM 12/91 232. GL-88-14 8107.MILLSTowE 1 M71681 INSTRtpqENT AIR SUPPLT SYSTEM Pe08tEMS AFFEti!#G SAFEff-RELATED EQUIPM - 10/91 233. GL-88-14 8107' NINE MllE POINT 1 M71685 lusfetsuENT AIR SUPPtY SYSTEM P208tEMS AFFEC4 tug SAFETT-RELAYED EQUIPM 12/92 234. GL-88-14 8107 ulwE MILE POINT 2 M71686 IwSYeUMENT A8R SUPPtf SYSTEM PROBLEMS AFFECiluG SAFEff-sttATED foulPM 12/92 235. GL-88-14 8107 OC04EE,1 M71689 INSituMEmi AIR SUPPtf SYSTEM PaOBLENS AFFEC11NG SAFETT-RELATED E00tPIE 12/92 236. 'GL-88-14 8107-OCONEE 2 M71690 ' luSTRtpeENT AIR SUPPLY SYSTEM P90E1 EMS AFFECTING SAFEff-eELATED Eculm 12/92 237. CL-88-14 8107 OCouEE 3 M71691 INSTaUMENT AIR SUPPLT SYSTEM P908tEMS AsFECTING SAFETT-RELATED EQUfPM 12/92 238. Gt-88-14 8107 OTSTER CREEE 1 M71692 IN1itt#EENT Alt SUPPtf SYSTEM P908tEMS AFFECTitG SAFlif-DELATES R;YlPM 03/93 239. ' Ct-88-14 8107 PAto VERDE 1 M71694 INSTRUW4T Alt SUPPtf SYSTEM Pt08tEMS AFFECilWG SAFEff-Retain WJim 12/91 240. GL-88-14 8107 PAto VERDE 2 .M71695. fusfruMENT AIR SUPPtv S' STEM P208tEMS AFFEtitNG SAFEff-RELATED EQUIPM 12/91 12/91 241. GL-88-14 8107 PALO vf RDE 3 M71696 luSistreEkT AIR SUPPtf SDSTEM PK18tEMS AFFECTlWS $AFETV-tELATED Eau 1PM ' 02/92 242. GL-88-14 8107 PEACM 80T10p 2 M71698 luSTeuMENT AIR SUPPtf SYSTEM PM8tEMS AFFECilWG SAFE 1V-ef t ATED EcutPM 243. GL-88-14 8107 PEACH BOTTOM 3 M71699

• t iTRUMENT AIR SUPPtY SYSTEM PR08tEMS AFFECTING SAFETY-DELATED EQU!PM 02/92 244 GL-88-14 8107 ob?" C T3ES 1 M71706 1=Sittp4E47 A!R SUPPLY SYSTEM PROBtEMS AFFECTING SAFEff-#EL ATED EcutPM 12/92 245.

GL-88 14 8107 OUAD rii!ES 2 M71707 - !=ST*UMENT AIR SUPPtf MSTEM P908tEMS AFFECT!mG MFEiv-ptLAFED f ourPM 12/92

5 IMPL ISSUE MFA PL ANT TAC TITLE DATE 246. GL-88-14 8107 SAN DWOFRE 1 M71713 INSTRtPEmi AIR SUPPLY SYSTEM PROBLEMS AFFEC18tG SAFETY-RELATED E00!PM 02/93 247. GL 88 14 8107 THREE MjlE ISL AND 1 M71730 thSflN. Pest AIR SUPPLY sistEM PROBLEMS AFFECTimG SAFETY-RELATED EQu!PM 12/91 248. Gt-88-17 LETT BE AVER VALLEY 1 M69723 LOSS OF DECAY MEAT REMOVAL 02/93 249 GL-88-17 L817 BE AVER VALLEY 2 M69724 LOSS OF DECAY MEAT REMOVAL 03/92 250. GL-88-17 L817 87RON 1 M76715 LOSS OF DECAY MEAT REMOVAL 11/91 251. GL*88-17 L817 CALVERT CLIFFS 1 M69730 1055 0F DECAY MEAT REMOVAL 0$/92 252. GL-88-17 t817 CAlvfRT CLIFFS 2 M69731 LOSS OF DECAY MEAT REMOVAL 05/93 253. Gt-88-17 L817 COMAECNE PEAK 1 M69/34 (CSS OF DECAY HEAT REMOVAL 11/91 254 GL-88-17 t817 0 C C00K 1 M6G736 LOSS OF DECAY HEAT REMOVAL 06/92 255. GL-83-17 L817 0 C COOK 2 M69737 LDSS OF DECAY MEAT REMOVAL 06/92 256. GL-28-17 L817 DAY 15-8tSSE M69739 LOSS OF DECAY MEAT REMOVAL 06/92 257. GL-88-17 L817 MADCAM NECK M69746 LOSS 08 DECAY MEAT REMOVAL 11/91 g 3 258. GL-88-17 L817 lhDfAu Polut 3 M69749 LOSS OF DECAY HEAT REMOVAL 05/92 O 259. GL-88-17 L817 MCQJ1RE 1 M69752 LOSS OF DECAY MEAT REMOVAL 12/91 260. GL-88-1T L817 MCGUIRE 2 M69753 LOSS OF DECAY HEAT REMOVAL 12/91 261. GL-85-17 L817 CCONEE 2 M69759 LOSS OF DECAY HEAT REMOVAL 12/91 262. CL-88-17 t817 PALD WERDE 1 M69762 LOSS OF DECAY MEAT REMOVAL 06/92 263. GL-88 L817 PALO VERDE 2 M69763 LOSS OF OECA? MEAT REMOVAL 01/92 264 GL-88-17 L817 PALO VERDE 3 M69764 1055 0F PECAY HEAT REsovAL 10/91 265. GL-88-17 L817 PRA!RIE ISLAND 1 M69767 LOSS OF DECAY MEAT RE*UVAL 12/91 266. GL 88-17 L817 PRAIRIE ISLAND 2 M69768 LDSS OF DECAY WEAT REMOVAL 12/91 267 GL-88-17 L817 SALEM 1 M69771 LOSS OF DECAY MFAT REMOVAL 07/92 268. GL 88-17 L817 SALEM 2 M69772 1055 0F DECAY MEAT REMOVAL 06/92 269 GL-88-17 L81T SAN ONOFRE 1 M69773 LOSS OF DECAY NEAT REpovat 12/91 270. GL-88-17 L817 SAW OuofRE 2 M69774 LOSS OF DECAY MEAT REmovAt 11/91 ' 2 71. GL 17 L817 SAM ONOFRE 3 M69775 LOSS OF DECAY DEAT REMOVAL 04/92 2 72. GL-88-17 L817 SEA 8 ROOK 1 M69776 LOSS OF DECAY NEAT REmovAt 02/92 2 73. CL-88-17 L817 TROJAN M69786 LOSS OF DECAY MEAT RE W AL 12/94 2 74. Gt-88-17 L817 TURKEY POINT 3 N69787 LOSS OF DECAY MEAT PEMovat 12/92 275. Gt 88-17 L817 TURKEY Potut 4 M69788 LOSS OF DECAY MEAT REMOVAL 12/91 2 76. CL-88-17 L817 ZION 1 M69795 LOSS OF DECAY HEAF RTMovat 06/92 277. Ct-88-17 L817 ZION 2 M69796 LOSS OF DEtAY MEAT PEMov4L 05/92 278. Gt-89-13 L913 ARKANSAS 1 M73961 SERVICE WATER SYSTEM PROSLEMS AFFECTING SAFETY REtATED EQUIPMEst 06/92 279. GL-89-13 L913 AR(ANSAS 2 M73962 SERvtCE 9ATER SYSTEM PROBLEWS AffECTING SAFETY RELATED E001PMEu? 12/92 280. GL-89-13 1913 BRAIDWOa) 2 M73969 SERvtCE kATER SYSTEM PR06LEMS AFFECTING SAFEYY ret ATED EQUIPMEst 12/91 ~

l i e IMPL ISSUE MPA PLANT TAC T!fLE DATE { -281. GL 89 L913 BROJNS FERRY 1 M73970 ' SERV!CE WATER SYSTEM PROGttMS AFTECTING SAFETY RELATED E001PMEuf 01/93 i 282. GL-89-13 1913 BROWNS FERRY 2 M73971 SERVICE WATER SYSTEM PROBLEMS AFFECTIM SAFETY RELATED EQU1Pu(NT 01/93 283. GL-89-13 L913 BROWNS FERRY 3 MT3972 SERV!CE WAYER SYSTEM PROBtEMS AFFECTfCG $4FETT SELATED EQUIPMENT 01/93 284 Gt-89-13 L913 BRUNSWICK 2 M73974 SERvtCE WATER SYSTEM PROBLEMS AFFECT 1mG SAFETT RELATED E001PMNT 11/91 f 285. Gt-89-13 L913 BYRON 1 M73975 SERVICE WATER SYSTEM PROBLEMS AFFECTlWG SAFETY RELATED EDU!FPENT 12/91 286. Gt-89-13 L913 BYRON 2 M73976 SERVICE WATER SYSTEM PROBLEMS AFFECT!kG SAFETT RELATED EQUIPMENT 12/91 1 287 Gt-89-13 L913 CatvERT CLIFFS 1 M73978 SERV!CE WATER SYSTEM PROBLEMS A8FECTING SAFETY RELATED ECalfPMENT 06/93 288. GL-89-13 1913 CALVERT Ct1FFS 2 M73979 SERV 1CE WATEE SYSTEM PROBLE"S AFFECitnG SAFETT RELATED EQUIPMEuf 06/93 289 CL 89-13 1913 CATnWBA 1 M73980 SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATE' EQUIPMENT 09/92 290. GL-89-13 1913 CAf8WBA 2 M73981 SERV!CE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EQUIPPENT 09/92 291. GL-89-13 1913 CLINTOE 1 M73984 SERV!CE WATER SYSTEM PROBLEMS AFFECT 1kG SAFETY RELATED EQUfPMEuf 03/92 ()

292, GL-89-13 L913 00arER 51 Aft 0m M73959 SERVICE WATER SYSYEM PROBLEMS AFFECituG SAFETY RELATED EQUIPMENT 12/91 a

293. GL-89-13 1913 DAVIS-8 ESSE M73991 SERvlCE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EQUIPMEuf 09/92 A 294 GL-89-13 L913 DIABLO CA= YON 1 M73992 ' SERV 1CE WATER SYSTEM PROBLEMS AFFECTIkG SAFETT RELATED foutPMENT 12/91 295. GL-87-13 L913 DIABLO CAuv04 2 M73993 SERV!CE WATER SYSTEM PRoetEMS AFFECitWG SAFITY RELATED EQUIPMENT 12/91 296. GL-89-13 t913 DRESDEw 3 M73996

• ERv!CE WATER SYSTEM PROBLENS AFFECT 1mG SAFETY RELATED EQUIPMENT 11/91 297.

Gt-89-13 L913 FARLEY 1 M73999 SEtytCE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EQUIPMEnf 12/92 298 GL-89-13 1913 FARLEY Z M74000 SERVICE WATER SYSTEM MROBLEMS AFFECTING SAFETT RELATED EQUIPMEuf 06/92 l' - 299. GL-89-13 L913 FITZPATRICR M74003 SERVICE WATER SYSTEM PROBLEMS AFFECT 1mG SAFETT RELATED EQUlPMENT 07/92 300. GL49-13 t913 FORT CALMOUM 1 M74004 SERvlCE WATER SYSTEM PROBLEMS AFFECituG SAFETY REL ATED EtKFIPMENT 12/91

301, GL-89-13 (913 G1444 M74007 SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETT RELATED EQUIPMEuf 12/91 302.

CL-89-13 - L913 GRAND GULF 1 M74008 SERVICE WATER SYSTEM PPOBtEMS AFFECTlwG SAFETY RELATED EGulPMENT 04/92 303. GL-89-13 L913 - MADDAM WEJC M74010 SEavtCE WATER SYSTEM PROBtEMS AFFECTING SA*ETT RELATED EQUIPMEuf 12/91 304 GL-89-13 L913 MATCH 1 M74012 SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETT RELATED EQUfPMEuf 01/92 305. GL-89-13 L913

• Aftn 2 M74013 SERV 1CE WATER SfsfEM PROBLEMS AFFECilWG SAFETT RELATED EQUtPMEuf 01/92 306.

CL-89-13 1913 NOPE CREEK 1 M74014 SERvtCE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EcutPMEuf 10/92 307. GL-89-13 1913-INDIAN Poluf 3 M74016 SERvlCE W4?ER SYSTEM PRGitEMS AFFECTING SAFETT RELATED EDUfPMENT 12/91 308. GL-89-13 L913-EEW4UNEE M74017 SERVICE WATER SYSTEM PR08tEMS AFFECTING SAFETY RELATED EQUIPMENT 11/91 309. GL-89-13 L913 LASALLE 2 M74019 SERvtCE WATER SYSTEM PROBtEMS AFFECTING SAFETT RELATED EQUIPMEuf 02/92 t f 310. GL-89-13 1913 LIMERICK 1 M74020 SERVICE WATER SYSTEM PROBLEMS AFFECTImG SAFETT RELATED EcU:PMENT 04/92 311. GL-89-13 L913 LIMrRICK 2 M74021 SERvlCE WATER SYSTEM PROBLEMS AFFECTimG SAFETT RELATED Ecu!PMEuf 04/92 312. GL-89-13 1913 M41RE YAmtEE M74022 SERvlCE WATER SYSTEM PR09tEMS AFFECTIwG SAFETT RELATED EcutPMEuf, 07/92 i 313. GL-89-13 L913 MCGUIRE 1' M74023 SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFEIT RELATED EQU!PMEuf 09/92 314. GL-89-13 1913 MCGutRE 2 M74024 SERVICE WATER SYSTEM PROStEMS AFFECTING SAFETY RELATED EQUIPMEnf 09/92 315. GL-89-13 L913 MitLSTONE 1 M74025 SERvlCE WATER SYSTEM PROBLE*$ AFFECTING SAFETV RELATED EQUtMut 07/91 i t

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Imt ISSUE 'MPA PLA41 TAC TITLE DATE ? f 351. GL-89-13 L913 SusaVEMANNA 2 M74072 SERVICE WATER SYSTEM P50BLEMS AFFECTING SAFETY RELATED EQUIPMEuf 12/92 l 352. CL-89-13 L913 TURKEY POINT 3 M74C76 SERvlCE WATER SYSTEM PPCOLENS AFFECTlWG SAFETY RELATED EQUIPMEuf 12/91 j 353. GL-89-13 (913 TURKEY PolNT 4 M74077 SERwlCE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EQUIPMENT 12/91 354 Gt-89-13 L913 40GitE 1 M74079 SERV!CE WATER SYSTEM PROBLEMS AFFECTING SAFEff RELATED EQUIPMENT 12/91 l 355. GL-89-13 L913-v0 GILE 2 M74000 SERVICE JATER SYSTEM PROBLEMS AFFECilNG SAFEff RELATED EGulPMENT 12/91 { 356. GL-89-13 L913 WATERFORD 3 M74081 SERvlCE WATER SYSTEM PRostEuS AFFECiluG SAFETY RELATED EaVIPMENT 02/92

357, GL-89-13, L913 WOLF CREEK M74088.. SERvlCE WATER SYSTEM PRostEMS AFFECTING SAFETY RELATED EOUIPMEuf 12/91 358.

GL-89 L913 ZION 1 M74090 SERvlCE WATER SYSTEM PROBLEMS AFFECTING SAFETY RELATED EUUIPMEst 12/91 359. GL-89-13 L913 ZION 2 M74091 SFRvlCE WATER SYSTEM PR0eltMS AFFECifuG SAFEff RELATED EQUIPMEmi 05/92 360. GL-90-C3 . LOO 3 BIG ROCK PolNT M76207 RELAX *110N OF STAFF POS IN GEN LETTER 83-28, ITEM 2.2 PART 2 10/91 361. GL-90-03' LOO 3 9RAIDWOOD 1 M76208 RELAKA710N OF STAFF POS IN GEN LElfER 83-28,. lTEM 2.2 PART 2 12/92 g 362. CL-90-03 . LOO 3 BRA DwacD 2 M76209 RELAxafl04 0F STAFF POS lu GEN LETTER 83-28. ITEM 2.2 PART 2 12/92 - 1 363. CL-90-03 LOO 3 - BRUNSulCK 1 M76213 RELAxAf ton OF STAFF PoS 14 GEN LETTEP 83-28. ITEM 2.2 PARY 2 12/92 W 364., Gt-90-03 LOO 3 stuuSWICK 2 M76214 RELAKAttou 0F STAFF POS IN GEN LETTER 83-28, IFEM 2.2 PART 2 12/92 'l 365f GL-90-03 LOO 3.BTRON 1 M76215 RELAXA110N OF STAFF POS la CEN LETTER 83-28 ITEM 2.2 PART 2 12/94 } 366. GL-90-03 LOO 3. BYR04 2 - M76216 RELAXAil04 0F STAFF POS f u CEN LETTER 83-28,' ITEM 2.2 PARY 2 12/94 367.. GL-90-03 1003 CATAWBA 1 M7622b. RELAXA1104 0F STAFF POS IN CEN LETTER 83-28, ITEM 2.2 PART 2 01/92 [ 368. GL-90-03 1003 CATAWEA 2 M76221 RELAXATIDW OF STAFF POS IN GEN LEtiER 83-28. ITEM 2.2 PART 2 01/92 t 369. GL-90-03 t003 DRESDEN 2 M76232 PYtaxAfl0N OF STAFF POS IN GFN LETTER 83-28, titM 2.2 PARY 2 12/92 3 70.. GL-90-03 LOO 3 DRESDEN 3 M76233 RELAxATIOw 0F STAFF POS In GEN LETTER 83-28, ITEM 2.2 PARY Z 12/92 371. GL-90-03 t003 luDIAN Poluf 2 M76247 RELANATION OF STAFF POS 14 CEN LETTER 83-28. ITEM 2.2 PART 2 12/91 l 372. GL-90-03. t003 LASALLE 1 M76250 RELAMAllou 0F STAFF POS 12 GEN LETTER 83-28, ITEM 2.2 PART 2 12/92 f 3 75. GL-90-03 L003 LASALLE'2 M76251 RELAxAilou 0F STAFF POS IN GEW LETTER 83-28, ITEM 2.2 PART 2 12/92 3 74. Gt-90-03 t003 ; MAINE TANKEE M76254-RELAXAfl0N OF STAFF POS lu gem LETTER 83-28, ITEM 2.2 PART 2 07/92 375. GL-90-03 LOO 3 NinE MILE Polaf 1 M76261. RELAkATION OF STAFF PDS fu GEu LETTFR 83-28. ITEM 2.2 PART 2 12/91 i ' 376.' GL-90-03 LOO 3 NINE Mite POINT 2 M76262 RELAXAf tou 0F STAFF POS IN GEN LEf fER 83-28, ITEM 2.2 PART 2 12/91 l .377. 'GL-90-03 . LOO 3 PitGR!M 1 J M76276' RELARAfl04 0F STAFF POS th GEN LETTER 83-28. ITEM 2.2 PART 2 01/93 f 178. GL-90-03 LOO 3 cuAD Cli!ES 1.

M76281 RELA 7ATION OF STAFF POS f u GEu LETTER 83-28, ITEM 2.2 PART 2 12/92 379.

GL-90-03 1003 QUA0 CiflES 2 - M76282 RELANs TION OF STAFF POS f u GEN LETTER 83-28, ITEM 2.2 PART 2 12/92 l 380. GL-90-03' LOO 3 SAs ONOFRE 1 M76288 RELAKPilos OF STAFF POS 15 CEu LETTER 83-28, ITEM 2.2 PART 2' 10/91 i 381. GL-90-03 LOO 3 SAu OworRE 2 M76289 REL AKAFION OF STAFF POS 14 GEN TETTER 83-28, ITEM 2.2 PAR 1 2 11/91 382. GL-90-03 LOO 3 SAN ONOFRE 3' M76290 #EtARATIOu 0F $1AFF POS la CEN TETTER 83-28. ITEM 2.2 PART 2 11/91 383. GL-90-03 -- t003 Sut#v 1 .M76300 RELARAtl04 OF STAFF POS la GEN LETTER 83-28. IFEM 2.2 PART 2 09/91 384.- Ct-90-03 ' LOO 3 SURRY 2. M76301. RELAN ATION OF ST AFF POS IN GE4 LETTTR 83-28, ITEM 2.2 PART 2 09/91 385. GL-90-03 LOO 3 TROJA4' M76305 REtamAf f 04 Or ST AFF POS is CEu (ETTER 83-28. ITFM 2.2 PART 2 02/92 i

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1. cM iso 2 3201. 32o2 BIBLIOGRAPHIC DATA SHEET

• • ' " C"Y-)

to insin= tion on in. reve'ai NUREG-1435 i tale Ano svemLE Supplement 1 3, DATE htPORT Puut i NLD Status of Safety Ir. sues at Licensed Power Plants MONTH YEAR nil Action Plan Requirements December 1991 Unresolved Safety Issues 4, m OR oRANT NuMuER Generic Safety issues 5 AUTHOR (b;

6. TYPE OF HLPORT Annual

r. PERoo CovEReo orciusiv. oston ADORE 6s t E

!vna or'. 'Jn 48. Nucmar Hegu story Cornmiss6an,.nd

6. PLRFOR.MsNQ OR,GANIZ ATION = NAME A.ND.nd memng ac e

memna ddress; e aoniractor, provid. nam Program Management, Policy Development and n. w Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

9. 6PONSORING ORGANIZATION - NAME AND ADDRESS (If NRC. type ' Sam.

[prwide Division, Office or Region, m =.. i. U.S. Nuclear Regulatory Commission, and malling address.) Same as above

10. SUPl'LLMENT ARY NOTE 6

11. ABSTAACT (200 words or less)

As part of ongoing U.S. Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This infor-mation was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of Dree Mile Island (I'MI) 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). His annual NUREG report combines these volumes into a single report and provides updated information as of September 30,1991. The data contained in these NUREG reports are a product of the NRC's Safety issues Managemeni System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Re;;ulation and by NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TML Action Plan Requirements, safety issues designated as USIs, and GSIs that have been resolved and involve in plementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933. "A Prioritization of Generic Safety Issues," whi-5 tracks safety issues up until requirements are appreved for imysition at licensed plants or until the NRC issues a ryest for action by licensees.

12. KEY WOODS /DESCRIPTOAS (List words or phrases that will assist researchers in locating the report.)

13, AVAILABILITY STATEMENT Unlimited Status of Safety Issues

14. SECURITY CLASSlFICATION Licensed Power Plants

(*' 80 Bil Action Plan Requirements Unclassified Unresolved Safety Issues (This Report) Generic Safety issues Unclassified

16. NvMDER 06 PAGES

16. PRICE NRC FORM 335 (2-89)

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