ML20127P427

Discusses Implementation of Regulatory Reform on Final Rule Re Mod to Operating Reactor Event Reporting Requirements (10CFR50.72 & 50.73).Recipients Requested to Attend Meeting on 920824.W/final Rulemaking Package & Summary of Comments

ML20127P427
Person / Time
Issue date:	08/19/1992
From:	Jordan E NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Beckjord E, Murley T, Norry P NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML19341G201	List: ML20127P401 ML20127P427 ML20127P448
References
FRN-57FR41378, RULE-PR-50 AD03-2-002, AD3-2-2, NUDOCS 9302010285
Download: ML20127P427 (43)

Text

{{#Wiki_filter:paM% UNIT ED ST A1 ES y, 4 NUCLE AR REGULATORY COMMISSION e 3.n - n W ASW NGT ON. D. C. 20LLS d~C 5 ,i / .P'Dd an AUG 191992 MEMORANDUM iOR: Thomas E. Murley, Director, NRR Eric Beckjord, Director, RES Patricia G. Norry, Director, ADM Gerald F. Cranford, Director, IRM James Lieberman, Director OE Martin G. Maisch, Deputy General '.ounsel FROM: Edward L. Jordan, Director, AEOD

SUBJECT:

IMPLEMENTATION OF REGULATORY REFORM - FINAL RULE ON tiODIFICATION TO OPERATING REACTOR ~ '4T REPORllNG REQUIREMENTS - 10 CFR 50.72 AND Su A memorandum from President Bush, dated April 29, 1992, addressed to certain ueprtment and Agency Heads, requested that addressees set aside the next 120 days to implement the previously identified regulatory reforms. The President went on to state that reforms reqairing public comment should be noticed no later than June 15, 1992, with a view tc issuing the final rules no later than August 27, 1992. The SRM, dated June 1, 1992, reiterated these completion dates for the eight ongoing rulemakings, including the subject rule. In a meeting on Friday, August 14, 1992, for the six of these rulemakings, various office representatives discussed their comments and concurred on the final rulemaking packages. On June 26, 1992, the NRC published the Notice for Proposed Rulemaking on the subject rule. A 30-day public comment period ended on July ??,1992. A final rulemaking package conr.isting of a Federal Register Notice developed by my staf f is enciesed for your concurrence (Enclosure 1). This package is due to the EDO by August 26,1992,for publication in tne Federal Reqister. Fcr your reference, Enclorure 2 contains a summary of comments on our resolutions. To expedite concurrence for this rulemaking, I request your attendance in a meetir.g at 2:00 p.m., on August 24, 1992, in room MNBB-9104. Please atter.d the meeting and provide you, concurrence or those changes to the Federal Register Notice that are necessary for your concurrence. If you cannot attend personally, please have scmeone attend who is designated to concur for you. If you prefer, please respond by telephone concurrence to Raji Tripathi of my staff (492-4435).

• /

Edwara . Jordan,Dir/ector Office for Analysis and Evaluation of Operational Data

Enclosures:

1. Final Rulemaking Package

2. Summary of Comments cc: J. Taylor, EDO 9302010285 930129 PDR PR 50 57FR41378 PDR

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~ I l 'l August 19, 1992 MEMORANDUM FOR: Thomas E. Murley, Director, NRR Eric Beckjord, Director, RES Patricia G. Norry, Director, ADM Gerald F. Cranford, Director, IRM James Lieberman, Director OE Martin G. Melsch, Deputy General Counsel FROM: Edward ). Jordan, Direct or, AE00

SUBJECT:

IMPLEMENTATION OF REGULATORY REFORM - FINAL RULE ON MODIFICATION TO OPERATING REACTOR EVEN1 REPORTING REQUIREMENTS - 10 CFR 50.72 AND 50.73 A memorandum from President Bush, dated April 29, 1992, addressed to certain Department and Agency Heads, requested that addressees set aside the next 120 days to implement the previously identified regulatory reforms. The President went on to state that reforms requiring public comment should be noticed no later than June 15, 1992, with a view to issuing the final rules no later than August 27, 1992. The SRM, dated June 1,1992, reiterated these completion - dates for the eight ongoing rulemakings, including the subject rule. In a meeting on Friday, August 14, 1992, for the six of these rulemakings, various office representatives discussed their comments and concurred on the final rulemaking packages. On June 26, 1992, the NRC published the Notice for Proposed Rulemaking on the subject rule. A 30-day public comment period ended on July 27, 1992. A final rulemaking package consisting of a Federal Register Notice developed by my staff is enclosed for yner concurrence (Enclosure -1). This package is due to the EDO by August 26, 1992 for publication in the Federal Register. fcr your reference, Enclosure 2 contains a summary of comments on our resolutions. To expedite concurrence for this rulemaking, I request your attendance in a meeting at 2:00 p.m., on August 24, 1992, in room MNBB41104 Please attend the meeting and provide your concurrence or those changes to the federal Register Notice that are necessary for your concurrence. If you cannot attend personally, please have someone attend who is designated to concur for you. If you prefer, please respond by telephone concurrence to Haji Tripathi of my staff (492-4435). original /s/ by D. F. Ross, Dr. /for/ Edward L. Jordan, Director Office for Analysis and Evaluation of Operational Data

Enclosures:

Distribution: 1, Final Rulemaking Package TPAB R/F

2. Summary of Comments DSP R/F AEOD R/F cc: J. Taylor, EDO

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s [(pmay),, UNITED STATES I < 'g NUCLE AR REGULATORY COMMISSION l W ASmNG T ON, D. C. 20$55 9, e %,...../ MEMORANDUM FOR: James M. Taylor Executive Director for Operations FROM: Edward L. Jordan, Director Office for Analysis and Evaluation of Operational Data

SUBJECT:

FINAL RULE -- MODIFICATION OF OPERATING REACTOR EVENT REPORTING REQUIREMENTS - 10 CFR 50.72 AND 50.73 Enclosed for your signature and publication in the, Fad.fral Reaister is the final rule modifying powar reactor event reporting requirements (Enclosure 1). Also enclosed are the Congressional Letters notifying the oversight committees of this action (Enclosure 2). The Federal Register Notice for Proposed Rulemaking was published on June 26, 1992, and the 30-day comment period ended on July 27, 1992. In conformance with the President's directive to reduce regulatory burden, and also in compliance with the SRM, dated June 1,1992, we reduced the public comment period from 75 to 30 days. You will recall that both the ACRS and the CRGR had deferred their revicw of this rulemaking until after public comment resolution. However, to be able to meet the expedited schedule for L publication of the final rule, we by-passed both Committees. The Committees, however, were apprised of the public comments received and aur resolutions. We received 19 comments - 2 from individuals, 3 from industry-supported organizations, and 14 from utilities. All except two respondents we' comed the y NRC's eff orts to reduce the licensees' and the NRC's resources. As expected, the utilities arid the industry-supported organizations expressed their desire for a broader relaxation to include all invalid ESF actuations from reporting. Based on the input from two utilities, we expect that these amendments will reduce the industry's reporting burden by about 15 percent. Our estimated savings of the NRC's response burden is about 5-10 percent. We have resolved all comments and have developed this package for the final rule. The Statement of Consideration has been modified and it refers to l NUREG-1022, Revision 1, for additional guidance on event reporting. The L wording of the final rule remains the same as it was in the proposed rule. l These amendments would have no impact on the NRC's ability to fulfil its. l mission to ensure public health and safety because the reporting reouirements that the Commission has deleted have little or no safety significance. This rule package has been concurred on by NRR, RES, ADM, IRM, OE, and OGC. l {. [_

s If you have any questicns, please call me on 492-4848. Edward t.. Jordan, Director Office for Analysis and Evaluation of Operational Data

Enclosures:

As stated W P l

l. s t. 1 If you have any questions, please call me on 492-4848. Edward L. Jordan, Director Office for Analysis and Evaluation of Operational Data

Enclosures:

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t I i [7590 01] I NUCLEAR REGULA10RY COPJilSS10N 10 CFR Part 50 RIN 3150-AE12 APT Minor Modifications to 4uclear Power Reactor Event Reporting Requirements AGENCY: Nuclear Regulatory Commission m ACTION: Final rule.

SUMMARY

The Nuclear Regulatory Commission (NRC) has amended its regulations to mako minor modifications to the current nuclear puwer reactor event reporting requirements. These auendnients will apply to all nuclear power reactor licensees and will delete reporting requirements for some events that have been determined to be of little or no safety significance. These amendments will reduce the industry's reporting burden and the NRC's response burden in event review and assessment. EFFECTIVE DATE: (30 days after publication in the Federal Register). FOR FURTHER INFORMATION CONTAC1: Raji Tripathi, Of fice for Analysis and Evaluation of Operational Data, D.S. Nuclear Regulatory Commission, Washington DC ?0555. Telephonc (301) 492-4435. 1 4 - - _ ~ _ - _ _ _ _ -. _ _. - - - _. - _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. _ - - - _ _ _. _ _ _ - _ _,

1 t l SL'PPLEMENTARY INFORMATION: QRApy

Background

The Commission has made minor amendments to the nuclear power reactor event reporting requirements contained in 10 CFR 50.72, "Immediate Notification Requirements for Operating Nuclear Power Reactors," and 10 CFR 50.73, " Licensee Event Reporting System," as part of its ongoing activities to improve its regulations. Specifically, this rule amends 10 CFR 50.72 (b)(2)(li) and 10 CFR 50.73 (a)(2)(iv). Over the past several years, the NRC has increased its attention to event reporting issues to ensure uniformity, consistency, and completeness in event reporting. NRC's reviews of operating experience and the patterns of licensees' reporting of operating events since 1984 have indicated that reports on some of these events are not necessary for the NRC to perform its safety inission, and continued reporting of these events would not contribute useful information to the operating reactor events database. Additionally, these unnecessary reports would have continued to consume both the licensees' and the NRC's resources that could be better applied elsewhere. Over the past several years, the NRC has increased its attention to event reporting issues to ensure uniformity, consistency, and completeness in reporting. As a result, in September 1991, the NRC's Office for Analysis and Evaluation of Operational Data (AE00) issued for comment a draft 2

..a a ..ar .g m _.- a u. x t NUREG-1022, Revision 1,' " Event Reporting Systems 10 CFR 50.72 and 10 CFR 50.73 -- Clarification of NRC Systems and Guidelines For Reporting." Following resolution of public comments, the NUREG will ;ontain improved guidance for event reporting. The NRC's continuing examination of reported events during development of this document has determined that certain types of events, primarily involving invalid engineered safety feature (ESF) actuations, are of little or no safety significance. Valid ESF actuations are those actuations that result from " valid signals" or from intentional manual initiation, unless it is part of a pre-planned test. Valid signals are those signals that are initiated in response to actual plant conditions or parameters satisfying the requirements for ESE initiation. Invalid actuations are by definition those that do not meet the criteria for being valid. Thus, invalid actuaticns include actuations that are not the I result of valid signals and are not intentional manual ar.tua+ ions. Invalid actuations include instances where instrument drift, spurious signals, human error, or other invalid signals caused actuation of the ESF (e.g., jarring a cabinet, an error :. use of Jumpers or lifted leads, an error in actuation of l switches or contrals, equipment failure or radio frequency interference). l l A free single copy may be requested by writing to the Distribution and Mail l Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555. A l copy is also available for inspection or copying for a fee at the NRC Public Document Room, 2120 L Street, NW., (Lower Level), Washington, DC 20555. 3 l l

t i hRC's evaluation of both the reported events since January 1984, when the existing rules first became effective, and the comments received during the Event Reporting Workshops conducted in Fall of 1990, identified needed improvements in the rules. The NRC determined that invalid actuation, isola-tion, or realignment of a limited set of ESFs or their equivalent systems, subsystems, or components (i.e., an invalid actuation, isolation, or re-alignment of only the reactor water clean-up (RWCV) system, the control room emergency ventilation (CREV) system, the reactor building ventilation system, the fuel building ventilation system, or the auxiliary building ventilation system) are of little or no safety significance. These events were reportable under 10 CFR 50.72 (b)(2)(ii) and 10 CFR 50.73(a)(2)(iv) which became effective on January 1, 1984. DRAFT The final rules for the current event reporting regulations,10 CFR 50.72 and 10 CFR 50.73 (48 FR 39039; August 29,1983, and 48 FR 33850; July 26, 1983, respectively), stated that ESF systems, including the reactor protection system (RPS), are provided to mitigate the consequences of a significant event. Therefore, ESFs should (1) work properly when called upon and (2) should not be challenged frequently or unnecessarily. The Statements of Consideration for these final rules also stated that operation of an ESF as part of a pre-planned operational procedure or test need not be reported. The Commission noted that ESF actuations, including reactor trips, are frequently associated with significant plant transients and are indicative of events that are of safety significance. At that time, the Commission also required all ESF actuations, including the RPS actuations, whether manual or automatic, valid or invalid -- except as noted, to be reported to the NRC by telephone 4

+, i l l within 4 hours of occurrence followed by a written Licensee Event Report (LER) within 30 days of the incident. This requirement on timeliness of reporting remains unchanged. The reported information is used by the HRC in confirmation of the licensing bases, identification of precursors to severe core damage, identification of plant specific deficiencies, generic lessons, review of management control systems, and licenste performance assessment. Q Discussion The NRC has determined that some events that involve only invalid LSF actuations are of little or no safety significance. However, not all invalid ESF actuations are being exempted from reporting through this rule. The relaxations in event reporting requirements contained in the final rule apply only to a narrow, limited set of specifically defined invalid ESF actuations. These events include invalid actuation, isolation, or realignment of a limited set of ESFs or their equivalent systems, subsystems, or components (i.e., an invalid actuation, isolation, or re-alignment of only the RWCU system, or the CREV system, reactor building ventilation system, fuel building ventilation system, or auxiliary building ventilation system). The actuation of the standby gas treatment system following an invalid actuation of the reactor building ventilation system is also exempted fron reporting. In addition, the final rule would also exclude invalid actuations of these ESFs (o, their equivalent systems) from signals that originated from non-ESF circuitry. 5

t However, invalid actuations of other ESFs wculd continue to be reportable; e.g., emergency core cooling system isolations/actuations, containment isolation valve closures that affect cooling systems, main steam flow, essential support systems, etc., containment spray actuation, and residual heat removai system isolations (or systems designated by any other names but designed to fulfil the function similar to these systems, and their equivalents). If an it. valid FSF actuation reveals a defact in the system so that the syst'.>m failed or would fail to perform its latended function, the event continues to be reportable under other requirements of 10 CFR 50.72 and 10 CFR 50.73. If a condition or deficiency has (1) an rd'-rse impact on safety-related equipment and consequently on the ability to shut down the reactor and maintain it in a safe shutdown condition, (2) has a potential for significant radiological release or potential exposure to plant personnel or the general public, or (3) would compromise control room habitability, the event / discovery continues to be reportable. DRAFT Invalid ESF actuations that would be excluded by this final rule, but occur as a part of a reportable event, would continue to be described as part

f the reportable event.

The proposed amendments are not intended to preclude submittal of a complete, accurate, and thorough description of an event that is otherwise reportable under 10 CFR 50.72 or 10 CFR 50.73. The Commission relaxed only the selected event reporting requirements specified in this final rul e. Licensees are still required under 10 CFR 50, Appendix 8, " Quality Assurance Criteria for Nuclear Power Plants and fuel Reorocessing Plants," to 6 d v

l 1 addeess corrective actions for events or conditions that are adverse to quality whether the event is reportable or not, in addition, minimizing ESF actuations (such as RWCU isolations) to reduce operational radiation exposures associated with the investigation and recovery from the actuations, are consistent with Al. ARA requirements. DRApy The provisions in 10 CFR 50.72 (b)(2)(ii) and 10 CFR 50.73 (a)(2)(iv), required the reporting of an event or condition that results in a manual or automatic actuation of an ESF, including the RPS, except when the actuation results from and is part of the pre-planned sequence during testing or reactor operation. A pre-planned sequence implies that the procedural step intilcates the specific ESF or RPS actuation that will be generated and control room personnel are aware of the specific signal generation before its occurrence or indication in the control room. However, if the ESF, including the RPS, actuates during the planned operation or test in a way that is not part of the planned procedure, such as at the wrong step, the event is reportable. The Commission has made additional relaxations to event reporting by excluding three additional categories of events as follows: (1) Thc first category excludes events in which an invalid ESF or RPS actuation occurs when the system is already properly removed from service if all requirements of plant procedures for removing equipment from service have been met. This would include required clearance documentation, equipment and control board tagging, and properly positioned valves and power supply breakers. 7

1 I (2) The second category cariudas events in which an invalid ESF or RPS actuation occurs after the safety function has already been completed (e.g., an invalid containment isolation signal while the containment isolation valves are already closed, or an invalid actuation of the RPS when all rods are fully inserted). r[lidESF (3) The third category excludes events in h actuation occurs that involves only a limited set of ESFs [i.e., when an invalid actuation, isolation, or realignment of only the RWCU system, or any of the followir.g ventilation systems: CREV system, reactor building ventilation system, fuel building venti-lation system, auxiliary building ventilation system, or their equivalent ventilation systems, occurs), invalid actuations that involve other ESfs not specificaliy excluded, (e.g., emergency core cooling system isolations or actuations; containment isolation valve closures that af fect cooling systems, main steam flow, essential support systems, etc.; containment spray actuation; residual heat removal system isolations, or their ~ equivalent systems), would continue to be reportable. Licensees would continue to be required to submit LERs if a deficiency or condition associated with any of the invalid ESF cctuations of the RWCU or the CREV systems (or other equivalent ventilation systems) satisfies any reportability criteria under @50.72 and 550.73. 8

~ DRAPy Imoact of the Amendments on the Industry and Government Resources Relaxing the current requirement for reporting of certain types of ESF actuations will reduce the industry's reporting burden and the NRC's response burden. This reduction would be consistent with the objectives and the requirements of the Paperwork Reduction Act. These amendments would have no impact on the NRC's ability to fulfil its mission te ensure public health and safety because the reporting requirements that the Coi, mission proposes to delete have little or no safety significance. it is estimated that the proposed changes to the existing rules will result in about 150 (or 5-10 percent) fewer Licensee Event Reports each year. Similar reductions are expected in the number of prompt event notifications reportable under 10 CFR 50.72. Some respondents, in their comments in response te the Notice for Proposed Rulemaking, dated June 26, 1992, have submitted an estimate of about 15 percent reduction in their reporting burden, l Summary of Comments l The NRC received 19 comments - 2 from individuals, 3 from industry-supportet organizations, and 14 from utilities. All except two respondents welcomed the Commission's efforts to reduce the licensee burden, and in turn l also to save the agency's resources in event review and processing. The utilities and the industry-supported organizations expressed their desire for a broader relaxation to inch:de all invalid ESF actuations from reporting. 9 l l

s t Other comments from the respondents were concerning clarification of the definition of " valid" actuations, examples of events being exempted from reporting, consideration of plant-specific situations, exemption from reporting of the actuation of the standby gas treatment system following an invalid actuation of the reactor building ventilation system, and possibly extending relaxation of invalid actuations/isolations of RWCU from reporting to include the chemical and volume centrol system in a pressurized water reactor. The Statement of Consideration has been revised to address most of these concerns; other issues and clarifications concerning event reportability will be addressed in NUREG-1022. However, it is not practical for the Commission to address a plant-specific situation unless it relates to a generic concern. NAPy The Commission stresses that only certain specific invalid ESF actuations are being exempted from reporting through the present amendments. NUREG-1022, Revision 1 will contain specific examples and additional guidance on events which are presently reportable as well as those which are being exempted from reporting through these amendments. In the future, the Commission will give due consideration to other proposed relaxations from event reporting after the staff has had an opportunity to reassess the data needs of the agency and has performed safety assessments to justify initiating a separate general rulemaking. Until such time, all events not specifically exempted in these amendments would continue to be reportable. The two respondents who opposed the rule change expressed their concerns about eliminating the event reporting requirements, which may adversely affect 10

the fiRC's information database and ultimately affect the agency's ability 19 carry out its mission to public health and safety. The Commission has reviewed the scope of these amendments, and the agency's assessments of several hundred reactor-years of operational experience, and has subsequently concluded with a reasonable confidence that relaxation of these events from reporting will ne' affect the agency's ability to protect the public health and safety. DRAPy Based on the input rrom the utilities, these amendments will reduce the industry's reporting burden by about 15 percent. The estimated savings of the tiRC's response burden in event review and assessment is about 5-10 percent. Environmental Impact: Categorical Exclusion The !!RC has determined that this proposed regulation is the type of action described in categorical exclusions 10 CFR 51.22 (c)(3)(ii) and (iii). Therefore neither an environmental impact statement nor an environmental assessment has been prepared for this proposed regulation. ~ Paperwork Reduction Act Statement This proposed rule amends information collection requirements that are subject to the Paperwork Reduction Act of 1980 (44 U.S.C. 3501 et seq). This rule has been submitted to the Office of Management and Budget for review and approval of the paperwork reduction requirements, 11

s. i Because the rule would relax existing reporting requirements, public reporting burden for the collection of information is expected to be reduced. it is estimated that about 150 fewer Licensee Event Reports (NRC Form 366) and a similarly reduced number of prompt event notifications, made pursuant to 10 CFR 50.72, will be required each year. The resulting reduction in burden is estimated to average 50 hours per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of information. Based on the input from the utilities, these amendments will reduce the industry's reporting burden by aLout 15 percent. The estimated savings of the NRC's response burden in event review and assessment is about 5-10 percent. Regulatory Analysis The Commission has prepared a regulatory analysis on this final rule. The analysis examines the costs and benefits of the alternatives considered by the Commission. The anuiysis is available for inspection in the NRC Public R Document Room, 2120 L Street, NW, Lower Level, Washington, DC 20555. Single copies of the analysis may be obtained from: Raji Tripathi, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Telephone (301) 492-4435. 12

~ -. -. -- ~~ - r, t i Regulatory Flexibility Certification in accordance with the Pegulatory Flexibility Act of 1980 (5 U.S.C. 605 (B)), the Commission certifies that this rule will not, if piomulgated, have a significant economic impact on a substantial number of small entities. The proposed rule affects only the event reporting requirements -for operational nuclear power plants. The companies that own these plants do not fall within the scope of the definition of "small entities" set forth in the Regulatory Flexibility Act or the Small Business Sizc Standards set out in regulations issued by the Small Business Administration Act in 13 CFR Part 121. DRAFT 8aafit Anaissis As required by 10 CFR 50.109, the Commission has completed an assessment of the need for Backfit Analysis for this rule. These amendments include relaxations of certain existing requirements on reporting of information to the NRC. These cnanges neither impose additional reporting requirements nor require modifications to the facilities or their licenses. Accordingly, the NRC has concluded that this rule does not constitute a backfit and, thus, a backfit analysis is not required. l l l 13

I ^ t List of Subjects in 10 CFR Part 50 Antitrust, Classified information, Criminal penalty, Fire prevention, Incorporation by reference, Intergovernmental relations, Nuclear power plants and reactors, Radiation protection, Reactor siting criteria, Reporting and recordkeeping. For the reasons set out in the preamble and under the authority of the Atomic Energy Act of 1964, as amended, the Energy Reorganization Act of 1974, as amended, and 5 U.S.C. 553, the Commission is proposing to adopt the following amendments to 10 CFR Part 50. DRAFT PART 50 DOMESTIC LICENSING 0F PRODUCTION AND UTILIZATION FACILITIES 1. The authority citation for Part 50 continues to read as follows: AUTHORITY: Secs. 102, 103, 104, 105, 161, 182, 183, 186, 189, 68 Stat. 936, 937, 938, 948, 953, 954, 955, 956, as amended, sec. 234, 83 Stat. 1244, as amended (42 U.S.C. 2132, 2133, 2134, 2135, 2201, 2232, 2233, 2236, 2239, 2282); secs. 201, as amended, 202, 206, 88 Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846). Section 50.7 also issued under Pub. L. 95-601, sec. 10, 92 Stat. 2951 (42 U.S.C. 5851). Section 50.10 also issued under secs. 101, 185, 68 Stat. 936, 955, as amended (42 U.S.C. 2131, 2235); sec. 102, Pub. L. 91-190, 83 Stat. 853 (42 U.S.C. 4332). Sections 50.13, and 50.54(dd), and 50.103 also issued under sec. 108, 68 Stat. 939, as amended (42 U.S.C. 2138). Sections 50.23, 50.35, 50.55, and 50.56 also issued under sec. 185, 68 Stat. 955 (42 14

U.S.C. 2235). Sections 50.33a, 50.55a and Appendix Q also issued under sec. 102, Pub. L. 91-190, 83 Stat. 853 (42 U.S.C. 4332). Sections 50.34 and 50.54 also issued under sec. 204, 88 Stat. 1245 (42 U.S.C. 5844). Sections 50.58, 50.91, and 50.92 also issued under Pub. L. 97-415, 96 Stat. 2073 (42 U.S.C. 2239). Section 50.78 als: issued under sec. 122, 68 Stat. 939 (42 U.S.C. 2152). Secticns 50.80 - 50.81 also issued under sec. 184, 68 Stat. 954, as amended (42 U.S.C. 2234). Appendix F also issued under sec. 187, 68 Stat. 955 (42 U.S.C. 2237). For the purposes of sec. 223, 68 Stat. 958, as amended (42 U.S.C. 2273); @s50.5, 50.46(a) and (b), and 50.54(c) are issued under sec. 161b, 68 Stat. 948, as amended (42 li.S.C. 2201(b)); @@50.5, 50.7(a), 50.10(a)-(c), 50.34(a) and (e), 50.44(a)-(c), 50.46(a) and (b), 50.47(b), 50.48(a), (c), (d), and (e), 50.49(a), 50.54(a), (i), (i)(1), (1)-(n), (p), (q), (t), (v), and (y), 50.55(f), 50.55a(a), (c)-(e), (g), and (h), 50.59(c), 50.60(a), 50.62(b), 50.64(b), 50.65, and 50.80(a) and (b) are issued under sec. 1511, 68 Stat. 949, as amended (42 U.S.C. 2201(i)); and @@50.49(d), (h) and (j), 50.54(w), (z), (bb), (cc), and (dd), 50.55(e), 50.59(b), 50.61(b), 50.62(b), 50.70(a), 50.71(a)-(c) and (e), 50.72(a), 50.73(a) and (b), 50.74, 50.78, and 50.90 are issued under sec. 1610, 69 Stat. 950, as amended (42 U.S.C. 2201(o)). I i 2. In 550.72, paragraph (b)(2)(ii) is revised to read as follows: l l @50.72 Immediate notification requirements for operating nuclear power l reactors. 15 l l l

i 8 (b) Non-Emergency Events. (2) four-hour reports. (ii) Any event or condition that results in a manual or automatic actuation of any engineered safety feature (LSF), including the reactor protection system (RPS), except when: (A) The actuation results from and is part of a pre planned sequence 1 during testing or reactor operation; (B) lhe actuation is invalid and: i IJJ Occurs while the system is properly removed from service; t 12). Occurr af ter the safety function has been already completed; or 111 Involves only the following specific ESfs or their equivalent systems: (i) Reactor water clean-up system; (iij Control room emergency ventilation system; (iii) Reactor building ventilation system: l (iv) fuel building ventilation system; or (v) Auxiliary building ventilation system. 16 w. --r- -,w. e

i A 3. In s50.73, paragraph (a)(2)(iv) is revised: 550.73 Licensee Event Report Syste:n. (1) Reportable events. (2) The licensee shall report: (iv) Any event or condition that resulted in a manual or automatic actual.lon of any enginecred safety feature (EST), including the reactor protection system (RPS), except when: (A) The actuation resulted from and was part of a pre-planned sequence during testing or reactor operation; (B) The actuation was invalid and: ill Occurred while the system was properly removed from service; L2J Occurred af ter the safety funct.on had been already completed; or D1 Involved only the following specific ESfs or their equivalent systems: (i) Reactor water clean-up system; (ii) Control room emergency ventilation system; 17

i (iii) Reactor building ventilation system; (iv) fuel building ventilat non system; or DRA8 ' # c* (v) Auxiliary building ventilation system. s s s + Dated at Rockville, MD, this day of , 1992. For the liuclear Regulatory Commission. 3amesMD~a~ilor, Executive Director for Operations, i { i l l l l l 18 o w .--y.

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il h FROM DATE COMMENT RESOLUTION yJ I l l l (OrgdContact) (SECY NO.) Wisconsin 1 7/27/1992 ' We would interpret chemical voleme control The NRC may consider initiating a more general g .i j i PubFe Service letdown system to be equivalent to the reactor rulemaking after the agency's need for future data. , Corporation water clean-up system in the rule. We believe that collection a:e ascenained, to address the set,pe of C. A. Schrock the proposed rule shotdd include a similar oWer suggested exemptions or additional 3 (contd.) exclusion for equivalent pressurized w2ter reactor reporting. If appropriate use examples suggested (PWR) systems as,ociated with the cleanup of the by the commenter in NUREG-1022, Raision 1. 0 3 primary and secondary water. For a PWR, we h believe that the exclusion of secondary water The analysis necessary to support a broader f cleanup U.e., steam generator blowdown) reduction in reporting requirements wouid delay i l l resulting from non-ESF signals would be issuance of this rule signincantly. Therefore, 1 l ll apprep-iate". comments proposing a significant change to the I Comment 3: ".. recommend clarification be scope of current rule are being dcferred. l provided for examp!es given in the discussion l i section of the proposed rule. R,is section We examined the definition ofinvalid ESF j considers reportable invalid actuations to include acturnions and the SOC cIcarly states that g l g ' containment isolation valve closures that affect relaxation of ordy the invalid actuations of l cooling systems.' 'ihis seems to imply that speciEed ESFs originating from non-ESF signals containment isolation valve closures (from non-are being exempted from reporting. l ESF signals'; that do not affect coolic; systems l are excluded from reporting requirements. Exa nples to consider would be containment isolation valves in the containment air sampling Gari6 cation of examples will be included in systems, the reactor coolant sampling system,s NUREG-1022. Revision 1. I [ sic] the containment vacuum breakers, etcetera'. t 5

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t v. t l' i s-i .g I FROM DATE COMMENT RESOLUTION 'I i f (OrgJContact) (SECY NO.) L L J j j South C1rolina. July 27,1992 " It is recommended 1:st 'ESF actuation' be We examined the definition of invalid ESF j j ' Ebetric & Gas (14) clarified to exclude the actuation of the dual actuations and the SOC clearly states 3:at i Company, John fur.ction (ESF and non-ESF) components by non-relaxation of only the invalid actua* ions of [ . L Sko'ds ESF logic. An example of this type of event is the specified ESFs originating from non-ESF signals. [ [ closcre of feedwater isolation valves due to a nea- ' are being exempted from reperting. I i ESF low flow / low temperature signal..The i-recommended clarification is as follows: L e i . Those components that provide a dual { function (e.g., ESF and non-ESF) and are i [ actuated as a result of a non-ESF actuation Suggasted wording appears to be OK for use'in I logic need not be reported. NUREalC22. l [ I ...all

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[ rerr. oval from reporting. review of past event } reporting at.. Summer.. did not identify any [ inva!id ESF actuations that were of ' safety i agnificance'...in these cases ESFs are being challenged unnecessarily, the number of such events are insignificant when compared to normal 3 surveillance testing of such components...one { cause of invalid ESF actuation, human error, has t i limited value in reporting as it is usually plant / site { [ specific and has limited applicability to the -) industry in general. Examples include the Disagree. Human factors assessment provides an' I f operation of wrong switches,' removing incorrect important insight into the licensee's performance. I I fuses, and inadequate procedures. t [ ' Union Electric 7/23/1992 Supports the rule as presented. OK! [ [ D. F. Schnell (3) i + t i t.

N __.--5 !I I FROM -DATE COMMENT RESOLUTION (Org./ Contact) (SECY NO.) [ _~ Centerior 7/28/1992 Toledo Edison supports the' comments preptred OK! Energy Davis-(17) by BWR Owners' Group and NUMARC. In Besse addition, re. 50.72(ii)(B)(1), proposes editorial change to shift from present tense to the past j tense. I i-In addition to " properly removed from service", li [ also include "when system was not required to be j operable according to the Technical Specifications'. j Centerior 7/27/1922 L "..CEI [ Cleveland Electric Illumiaating Company] Cannot address plant-specific ccafigurations or Energy (10) concurs in general with the proposed rule sitrations in the rule. Examples may te l g Perry changes..CEI endorses the comments provided by considered in NUltEG-1022, Revision 1. M. D. Lyster the BWR Owners Group". Ibwever, if the signal is known to be invalid then i the RWCU system actuation / isolation need not bc ...Because of certain design characteristics. the reported. l RWCU at Perry is susceptible to iscladons as a result of differential flow during rc,utine { operational maneuvers. The e isolations are Editorial comments Ol'! '} L-unpredictable and difficult to avoid, and have { resulted in numerous reportable events over the [ last several years. Engineering es aluations has l shown the system conditiens which cause the l t isolations to have no significant negative affects l on the system. Also, in Tch case, the isolation has occorred as designed, demonstrating a high level of reliability of the isolation system *. ESF definiden. We examiaed the defmition of invalid ESF l actuations urf the SOC clearly states that yl Additional comments on the Statement of relaxation of on'y the innlid actuatias of L Consideration and the marked-up copy of the specified ESFs originating from non-ESF signals l FRN. are being exempted from reporti.g g e { g o r -u = +

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O e 1 ! FROM DATE I COMMENT RESOLUTION l (Org../ Contact) (SECY NO.) f l P )BWROG 7/27/1992 .. commends the NRC for this effort.. OK! f* C. TtJly (4) ..cndorses the principal goal.. .. concurs with the proposed rule change. comments pnmanly on the Statement of OK! I l Considerations, mostly editorial. Y ~ Invalid actuationa of other ESFs, except those ne NRC may consider initiating a more general g noted above, would continue to be rulemaking after the agency's need for future dah g' reportable...As written, the sentence makes the collection are ascertained, to ad fress Ibc scope of corriusion that all invalid ESF actuations are other saggested exemptions or additional safety significant...The reporting rules are

reporting.

l intended to capture safety significant events, but experience has demonstrated that events that are Tne analysis necessary to suppert a broader g not safety significant are sometimes captured as reduction in reporting requirements would delay issuance of this rule significantly. Therefere, 2 well. ..Tne type of events discussed do not necessarily comments proposing a significant change to the constitute a reportable event under the current scope of current rule are Seing deferred. g l We examined the definition of invalid ESF rules. t actuations and the SOC clearly states that l relaxation of only the invalid acteations of I l specified ESFs originating from non-ESF signals l l are being exempted from reporting. j l Not tru I ! Detroit Edison 7/27/1992

• commends the NRC for this effort and other

' OK! W. S. Orser (11) related efforts to improve its reporting requirements... concurs with the propc. sed rule y change" l 1 An estimated 15 percent reduction in the number Licensee estimates abcut 15 percent reduction in burden - same as Florida Power and Light's of LERs. estimate. f

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. - - - ~ - - - -. ~ -.-. I c r }}00h 1 gy (Q 57FA W379 ppg 41378,.rederal kor,lster / Vol. 57. No.178 /, Thunday. Septernber 10.1WE / Rules tend Hegulationa L--..-._-- c crtified to OMll,in a IcHer dated for the Nuclear Replatory Comminion. r,o 72 and to CIH 5013-Clarification nf August 14.1tra2 that by unanimous vote f.ame. 4 I chltk. NRC Systems and Guidelines for the Comrnission had ovenidden the s,crea. v o/rAe comm/ salon-Heporting." Fellowing resolution of OHKs dippproval of the information im Doc..

• e l'iled 9+02, ats amj public comments. the NUREG will be issued in the fmal funn. %e NUREG collection request suociated with this sw o cuor rua.c.

tulo. will contam improved guidance for. On August 21,1d92. OMil assigned t'se event reporthis. following new control number: 3150 10 CFH Part 50 NRCs reviews of operating e Aperience and the patterns of licensees' 0171 efic(tive until August 31,1105. HIN S t$0-AC12 %ls new control number is only reporting of operating events since 1904 applicable to the sections in 10 Crp part Minor Modifications to Nuclear Power have indicated that reports on some 9f - 35 amended by this rule. Infortnation Reactor Event Reporting . these events are not necessary for the collection authority for all other sections Requirements NRC to perferm its safety mission and of 10 CI'R part 35 remains under the that continued reparting of these events esi$na Beneral control number 3t 50-ACCNer. Nuclear Regulatory would not contribute useful ltrmatio 3 Comudesin. C010. to the operating reactnr events AC pc Phal rule. database. Additionally, these Ust of Subjects in to CrR part 35 unnecessary reports would have tuuu Anr.The Nuclear Regulatory c ntinued to consume both the Dyproduct material. Criminal ienalty. Commlulon (NRC) has amended its licensees

• and the NRCs resources that l

Drugs, llcalth fac1htles.)1ce'Ith regulations to make rninor modincatlons could be better applied elsewhere.%e proiculons, incorporation by reference, to the cunent nuclear power reactor - NRC has deter..ined that certain types Medical devices, Nucicar materials, eventte rting requirements.%e fina9 of events, primarily those involving Ottupational safety,and hen!th-rule opp a to all nuclear power reactor invalid engineered safety feature (FSF) - Radiation protection Reporting and licensees and deletes reporting actuaums, ere oNule ofno safety recordkeeping sequirements requirements for some events that have Teat of Final Regulations been determined to be of little or no signlGcance. safety significance.ne final rule Valid ESF actuations are those For the reasons set out in the reduces the industry's reporting burden. actuations that result from

• valid preamble and under the authority of the and the NRCs response trutden in event signals" or from intentional manual Atomic Energy Act of 1954, as amended. review and assessment.

irdtlation, unless it is part of a, the F.nergy Roorgantration Act of 1974, ErrtCTtVC DAtc October 13.1992-preplanned test. Valid signals are those signal. that are initiated in response.to as amended, and 5 U.S.C. 552 and 553, mn mamm mmnuAnoN CNACn actual plant conditions or parameters the NRC is adopting the following a a - for ysls a atisf) the requirements for F.SF.. amendments to 10 CFR part 35; PART 35-MEDICAL USE OF Nuclear Regfalatory Commission. DYPR& DUCT MATERIAL, in ton,DC20555. Telephone (301) njaM a us ione a e by definitio - g 1.%e authorit citation for part 35 suretruthAdy wronManote hde IN's il at at ot t e result continues to rea in part as follows: g ggg Authority: Sece 101. 68 Stat. 948. no II manual actuations. luvalid actuations omended let U.SC 22011. sec. tot, sa Stat. %e Commission is issuing a final rule include instances where instrument 1242, as amended (42 U.S C. 564 tl * * *, that amends the nuclear power reactor drift, spurious signals, human error, or event reporting requirements contained other invalid signals caused actuation of

2. In i 35Ji, paragraph (b) is revised in 10 CPR 50J2 *1mmediate Notification goggow,,

the ESF (e.g., janing a cabinet, an error . and paragrsph (d)is added to'rcad as Requirements for Operating Nuclear in use of jumpers 4f lifted leads, an error power Reactors,** and to CFR 5053, in actuation of snitches or controls. l 9 35.s ' informauon conection "Ucensee Event Report System." ne - equipme it failure, or todio frequency l tcquirements: 0MO approvet. final rule is issued as part of the interforence). Commission's ongolng activities t events since January 1984, when tborte NRCs evaluatlou c!both the n (b) The approved information improve its regulations. Specifically, th's e . collection require nents contained in this final rule arnends 10 CIR 50J2 (b)(2)(li) existing rules first became effective, and and 10 CFR 5013 (a)(2)(iv). On June 20 - the comments' received during'the Event part appear in iI 35.12,35.13.3514, t 3521,35.21 3523,35.27,3529,35.31, 1992(57 PR 28042), the Commission Reportin Wo'rksh. ops"coriducted in Fall ~ 35 50,35 51. 33.53, 35.S9.35 00,35.01, . issued a proposed rule te sting p"bbc of W90i entified neede'd improvements comments on these amen ents. n the rules.%a NRC determined that ' 35.70, 35A0. 35.02; 35201. 35.205. 35.310, Over the past several years, the' NRC invalid act' attom isolstion, ce 35.3 t 5, 35.404. 35.400, 33.410, 35 415. u has increased its attention to event gg g gy, 35ml, 35410, 35.015. 35.630. 35E32, 35831. 35MS, 35.041/35 (W. 35bl5, and reporting issues to ensure smiminnity, including the si6tems, subystems, or I n pt >r10 i eNRCs C *1"'.nts Re., an IwaM actuaHon. is laum or reaugnment of only tha. Office for Analysis and Evaluation of reactor water clean up (RWCU) system, (d) OMB has assigned centvi number Operational Data (AEnn) toued for 3150-0171 for the infonnation collection

• comment a draft NUKl&1022, Revision e

requirements contained in il 35.32 and 1,8

• Event Ret orting Systems to CFR Nnia' 8terulate Caal** Wahl'#m Dc 35.33.

rosn A egy to also evel14ble hw 8 ispectma or t copying for a fee et the NRC Put>he Document DetNi at Rohlle. Maryland, th t 3d da y a tm,mde egy may be nqumed by wmtng to Imm. U301. Seed NW.,(uswer kvel). of September 11'91 the Dietribuuun and Mail Settkee t.ecuan. OS. - Washttpan. DC 2054, e

__ -, - _~.- y tl'ederel,ltegister /.Vol.N57. No..370 Flhursday, ficptember.10.19J2 / Riiles an'd l(egulations 41370 .c n 9 the control room emergency ventilation ventilation system, cualliary building . "Ihis. rule excludes three cateEories of (CRIN) system, the reactor building " ventilation system. or their tviv. lent events from reporting:,N ventiladon s)sictn. the fuel building veritilation systems).%e act.sation of (1)The first category exdudes events sentilation system, or the auxiliary the standby Fas t*catment systern in which an invalid ILF or ItpS o building sentdation system lor their following an invalid actaation of the actuation occurs when the system is.. equivalent ventilation s} stems) are of reactor building ventilation system is already properly removed front service httle or no sidety signihwce, llowever. also emernpted from reporting. In if all requirements of plant procedures - these events are cunently reportable edditiors the final rule excludes invalid for removing equipment from service under 10 CIR 50J2 (b)(2)(ii) and 10 Clh actuations of these USFs 'er their have been met.This hcludes sequired 5013 (a)(2)(lv). equivalent systems) from oignals that clearance documentatfort. vgulpment %a f;nal rules for. he cunent event t originated from non-ESP circuitry. and control board tagging, and properly reporting regulations.10 CIR 5012 und - {caltioned valves and tiower supply ik, wever, invulld actuations of other 10 CIR 5013 (4ft ilt :ttm9; August ;'9, red crs. 1^4 ar.d 4B IR 33050; July 2rl,1983. 13Fs would continue to be reportable, res ecuvely), sta:cJ that i$F systems. For example, emerSency core cooling (2)%e secod category excl des system isolations/actuellens. events in which an invalid ISF o'r RpS it,c udmg die reactor proter.tlon system contalnment isolation valve 'losuies actuation occurs after the sefety (PJS), are provided to triugate the dat affect coding systems. main stca.u function bss already been completed or,Ybra s$ ul ori j e con \\a 1 ,s nae p s ems E " e n ls I lon gaw e w II[r.Unile.f,Ifr ently or residualheat removale stemisolations va v a a ca los or a nvalid a unnecessarily. ne Statements of ( r sptems designated any'other Consideration for these final rules also names but designed to fu fdl the ioH inserte4.- stated that operatlon of an IEF as part function similar to these systemt and (3) ne third category excludes events of a pre planned opsrational procedure their equivalents), are still reportable. If in which an invaHd IEF octuation i or test need not be reported. The an invalid isF actuation reveals a occun that involes only a limited set of Commission noted that ESF actueions* defect in the system so that the system ESFs [i.e., when an invalid actuation. including reactor trips, are frequently failed or would fall to perform its isolauori, or reaUgnment of only the : anocialed whh significant plant intended fmiction, the event continues to @ systemar any of Ge foHowing transients and are indicative of events, be reportable under 6ther r(quirements ventilation systems: CREV system, that are of safety s;gnliscance. At that of 10 CFR 5032 and to CW $053. If a, reacim4ullding ventilation system, fuel time, the Commission also required all condition or deficiency has 1) en building ventilation system, euxiliary bF actuations, including the llpS adverse impact on safety-re{.ated building ventilation system, or their actuations, whether manual or equipment and conscquently oli the equMent vedadon systerns, Mcun[ automatic, valid or invalid-except as

• ability to rhut down the reactor and

, invalid actuations that involve other twted, to be tcported to the NRC by maintain it in a saio shutdown ESFs not specificall est.lodedl(e,g, telephone within 4 hours of occurrenw condition,(2) has a potential for ermgency em cm ing eystem. followed by a written IJcensee Event significant radiological release or isolations or actuations; containtuent iso anon vu cl sms that a&ct Report (IERI withla 30 days of the potential exposure to plant personnel or incident.%is requirement on timeliness the general public, or (3) wouki cwbng sys' ems, rmdn steam hw, of seporting remains unt. hanged. compmmise control room habitability. [n " lo. residual %e reported informatmn la used by the event / discovery continues to be P Y u the NRC in confirmation of the licensing reportable hI*"I'Y8"I'"I" bases, identification of precursors to invalid hSF actuations that are

1. 9" "

severe cor0 damage, identification of excluded l>y this final rule' lat occur a s l.icensees co" ntinue' to be' required to lant specific deficiencies, generic

• I" 8

8 8 "* casons, review of managemerit control wbmit IE.Rs if a deficiency or condition systems, and licensee perfonnance be siescrfbed as part of the reportabic associated with any of the invalid isF event.%ese amendments are not actuations of th RWCU or the CREV assessment. intended to preclude submittalof a. systems (or _9t equivalent venuladon Discussion complete, accurate, and thorough - syWstnj) saUs ses any reportability %e NRC has determined that some description of an event that is otherwise criteria under l 50J2 and i 50J3, t vents that involve only invalid ESF tcportable under 10 CFR f,072 oi to Cl R actuation are oflittle or no safety 50J3.%e Commission relased only the impact of the Amendments on the significance. lfowever, not al! Invalid selected event reporting requirements Industry and Government Resources ESP actuations are being exempted from specified in tids final rule. Relaxing the requirement for reporting reporting throuEh thle rule.%e IJcensees are still required under to of certain types of ESF actuatior.2, relaxations in event reporting. C111 part 60, appendix D. " Quality reduces the industry's reporting burden s. xquirements contained in the final rule Assurance Criteria for Nuclear Power and the NRC's response t>urden, %Is. A pply wly to e nancr*, limited set of Plants and Fuel Reprocessing lants," to reduction is consistent with the p e iccifically defined irvalid ESF address corrective actions for events or objectives and the requirements of the a ctueuons.%ese events include invalid conditions that are adverse to quality Puperwork Reduction Act.%ese. . ace = tion, Isolation, o* realignment of a whether the event is reportable or not.. amendments have no impact on the. limited set of ESPs including systems, in addition, minimizing ESF actuations ' N5tC's ability to fulfill its mission to ' . subsystems, or components (i.e., an . (auch na RWCU isolations) to reduce ensure public heahh and safety becau~se.. invalid actuation. Isol ttion, or. operational radiation exposuns the deleted reixn tability requirements. realignn. cal of only the RWUtisy:. tem, associated with the investigation and have little or no safety significance... or the CRtW system, suctor building - recovery from the actuations,4re. - It is estimated that the changes to the ventilation system, fuel building consistent with Al. ARA requirements.' nisting rulas wul tesult in hbout 150 (or r"-

( i 41'tatt Federal Hegister / Vol. 57..No.17U / Huruday, September to.11rJ?.'/ lhdes aud.lW,utathms 5-1ft perved) fewer (Jxnsee l>rtti their concerns about e?!mimrting the overepe 50 honts per licensee response. 'elercris eedi year. !untilar m!uchns sehrted emit reputilug ruqnfrements. Indudmg the time required reviewing arr espected ht the ntunber of ).rompt %ese commenters imbeve that the insttu-ilown, scart. Ling existhig data eveat naufrcatitme reportable imder 10 chmination of these event reporting sourtes, gathering and maintaining the CiN f 0 72. !bme respondents, in their requlteracuts enny advenely affect the data needed,argl eviewing the comments on Se gnepened rule, dhted NHC's infotaurtion dafabase and collection of hdorination. Lend J une.% 11H, sabrnia ted att estrmste of ultimately a!!ect the agency's ebflity to commenta sty,asdmg die esutaaled apprmdittetely 15 tertent reshm'hm in cu ry utit its enisstort to protect ptrblic burdeJi teda'. Wort or my other a6 pet t of theie

• Msting berden.

health ami safety. For rnany years, the this collection ofinformation,indading NitC stell hwa been systernaucal!Y suggestkurs for redudng dels burden, to 6"8W "I C"88^*"t* reviewinginknnatlat theined fron' the IrdonsetLost and Re'corde ?ti.WAc rtwived 19 ciannw s.ta- < tj, ensec F,veut hersorts.ucs' Mensgetuenn t) tench (MNIW77141. UA frorn indmduals,3 from industry-assessments of reactor opersthd Nuclear Repbiksy Con.Antukm, supported orgasdtt ttnna, and 24 (rom uj.crieme have ledaded data to the Washington, DC 20M; and b the Desk utilities. Ihttpt for tr in er*ranh't, au types of events indrahlin t!m three Ofheer,Ofure of Ir.formauors and commenters wekttw, Wi rateptics that the NitC is dele 6a hout Regulatory Allainr, Np.On-Mtti. (31W Comraission's eaforts t:c tede th-rtperting. We etalf's teyte'ws and rmt and 31'D401).Offu of licensee lmsden and to sieve the assenments of awarly 100b reattor" danagement ead Budget, Washington, agesty's resourtes in event review a rd years or operallonal esperience have !)C 20Mt1' procening. %e utditica and ttm Idunulled essentially no safety industry supporttd orpnfrarioni significants avoociated tvith the type o8 Hegulatory Analysier empressed thalt desire for a bmeder events toduded las Osa afosernentinned relaxa16 toladude allirwnhd IN three categories.ne Convulsaham bas ""I'y'I Q. actuations from sepurthig. reviewed the sco ie bI hoo , E" "I Othes na usents fiorn the rirspondeuts amendmenta, an on the basis of the %c analys!e namines dre costs and lwnents d die ehernedm consMered concemd i e f Mowing: d.irificaum of stairs aneument of the pet reactor i the deiunEc, o(

• tavalkf' actuations'.

operational raperience.has by the CommintonMe analyds is examples of evmts being emetapted subsequently umdudal with a available it,r inspection in the NRC f rom reporte crmiderath of pl nt' reasuusbla runfkience that relaxath I'ubtle Document Room. 2120 !, Street, NW., lenver 1meel. Washigfon. DC sprt$c situation exemption from from re porting of evecta la the tineo teposting of Ibn actuallon of Ae standby categories sk>e6 not affect tlw myency's 20%5. Singk copics of the analysis mey gas treatzacnt syskan followins an abihty to protect public headth and be obt taedfrotte!l.aKTripath!,Ofnce for Ana?ysis andINaluation of invalid aduathof the readm buildlag ufety, ventilath system. and assibly lined on the input frcm the millities. Operauonal Data, UA Nudear calendjng relaxat ou of invalid these amendmeute will reluce the Renfatory Commluton. Ws:.fdagh, ac.tuations/tsolaths of RWCU from industry's rep $ ting burden by about 15 DC 20%5. Telephone (301j 4't24435. reporti to Luclude those of the percent.The estimated savings of the Regulate:y flexibility Certificath cheml and volusna ccuirol systeu in NRC's n sponse burden in event review a pressurized wa ter seactor.%e ami assessment is about 5-10 perant. In ausadance with the Reguistray Statement of Cons;derations for this flexibility Act et 1mio ($ 11ACdaMil)). final rule thircases most of the.: , E"'I'eneutalImpada4xkal the Cornmissh certlfies that this rule I:ujunima does not hve a signifitant econcisic concer:ts. Otles inues and clutiv.ations concerning event reportabnity will be ne NRC has detennined that this impact on a subtantial mamtwe of saiali addrened in NURfL1022. l<evision 1. final ruleis the type of action described entitles.%e Gnalrule aHects only the llowever. it is not practical to address a in categorical exchelona 10 CFR 51.Z2 event reporting requkrements for plant epectfic situstion vrdeas it :clates (c)(3)(u) and lili).nerefoni, neither en openHonel mede%perwer pbh %e to a generic concer t. environmentalimpset statement nor an companh s that.own these plauts do not The Commission drenes that only environnientat ansessment has been fall within the scope of the deimith of certain specific luvulid 12ir actuations prepaml for this final ruin. small entities" nt forth in the are being exempted from reporting Paperwork Reduction Act Statement Regulatory l'iexibility Act or the Smsil through the present amemiments. IMWu SW Standanis um Iin NUREG-1022, Revision I will contain his final rule amcods htformation - regulations Inned by the Small lhistness specific examples and adchtional collection requirements that nre subject Administration Act in 13 CI'R part 121. guldance oc t%ents wbich are presently to th& paperwork Reduction Ad of 10 tic reportable as well es those whkh are _ (41 USC. 3501 et seql hese Duklit Analysis bemg exempted from reporting through amendments were approved by the As te9u red b to CFR 50.109, the I thvse amendments. La the future. the Office of Management and Budget Conuninion has cmnpfeted an Commission wilf give due consideration epproval munbers 3150-0011 and 31W smument of thes need for flackfit to other propond relaxations from 0104. event typorting after the NFC staff has IMcause the rule wi!! relar. existing Analysis for this final rule.ue bd an opportunity to reassess the data rt porting requirements, public reporting proposed arncmtments indude needs of the agency and performed burden of infortnation la espected to be selaxations of certain extsthig safety onessments to justify initisting a s educed. It is estimated that about 150 requirements on reporting of infonnation separate general rulerrud ing. t tatil sudi ' fewer IJcensee Event Repoils (NRC to the NRC.%ese changes neither time, all events not spedfically ~ ronn 306) and a alm!Iarly reduced impose additwnalrepmting exempted in these emendments continue number of prompt event notifications, requirements not require modifications to bc reportahtit made pursant ta lo CFR 5032, will be ta the facihties or their licenses. %e two respondents who opposed required each year. Ik reswhing Accordmgly, the NaC has coiwiuded Ae pngmed amendments c xpresm! reduction in bioden is estimated to that this fmni rulo does not runstitute a

4 i - [ ftdctul Register / Vola 67, fJo.170 / 'Ilmroday.&ptember 10, irrs/ Pulen er d:Hegulations41381' *. j .___a back fit and, thus, a barlfit snelysis is 2.In 6 !.0.7? pursgraph (b)(t)Di)is for the feudes Hegul.tary ComenulonJ a not requbed. revised to read as follows: James ht.Tath tjet of Subjects in 10 GTR Per150 { !,0.72 Frmedtste nottrkation Antitret, Classified information 4"I'ements fm operatmg nucleu swn W W W N e m M sm) Criminal penalty, fire prevention, ' Licorporation by reference. Intergovernmental relations. Nuclear (b)ffon cmergency I ents{ ' * (2)iour hour reports. DERAL f1ESERVE SYSTEM power plants and reactors Radiation pretection, Reactor siting criteria. (H) Any evetit or condition that results M NM Pad M Reporting and rizcordi ceping fri e manual or automatic actuation of for the reasons set out in the any engit.eered asfety feature (ESf), IRegulation Y, Docket No. F147061 prearnble and under the authority of d,e including the reactor protection systern Atomic F.nergy Art of 19GI, as amended. (RPS). except when! IUNI O D 8 the 1;nergy Reorgantration Act of 1ti74. (A)ne actuation results itom and is as amt nded, and 5 USC,552 and 55J. part of a pre-planned sequente during Bank Hokfing Companiet and Change in Dank Control the Commission is adopting the testing or reactor operation: IJowing arnendmenta to 10 CFR part (II) %e actuation is tnvalid and; AorNCY:ljoahl ol CoVernors of the

• E (1) Occurs while the eystern is rederal Resesve Systern.

properly removed from service; ACTION:l'inal rtde' PAFIT 50--001.tESTIC UCENSING OF (t) Occurs after the safety function Pi1000CT10N AND tmLIZATION has been already cornpleted; or supuAfm ne Doord is amending its FACIUTIES (J) Involves only the following specific flegulation Y to augment the list of 1.%e authortly citation for Part 50 is IIFs or their equivalent systems. permisalble nonbartkmg ectivities for revised to read as follows: (/) Reactor water clean.up system: bank holding compcnles to include the Authodty: Secs.102,103,104,10s,101, se2, (ii) Control room emergency provision of full servive securtiles, ventiladon system. brokerage under certain condidons; and 4. ni 1. se 234. 1 S t' (W) Reactor bullking untiladon the provision of financial edvisory 1254, as amended 142 UAC 213: 213s. 2134, system: services under certain conditions.He 22 n. um. nat us3. 2pa, 2.un. na2k sces. (/v) ruci building ventilation eystem:. Doard has.by order previously mpproved An. as amended. 202,206. 66 Stat.124 se or ~ these activities. Applications by bank emended.1244.324a(s2 USC 241.6842.. (v) Auxlhary building ventilatl6n holding companies to engage in. 6848). syste[m activities included on the Regulation Y Section Lo f also inued under Pub. L ob list of permissible nonbanking activities col. sec.10. 92 Stati2n51 (42 U.S C M51) Section Lo to also inucJ under sees.101. tas,

3. In $ Sa73, paragraph (a)(2)(ivj is Ina beIirocessed b the Reservellanks 68 Stal 930,9%. es emended [42 USC'2131, revised to read as follows:

un er expedited procedures pursuant to, 22351. sec.102. pub. L en-1m 83 Stat. ass (47 delegaled authority, U.S C 4332k tections m13. mW(dd), and {LOJJ Ucen6ea e**nheport system. EfrrCTfvt Daft: September 10,1tXt2, bo.103 also leaved under sec. lon. 64 Stat.9N. ' la) Reportable eventa. * *

• FOR FURTHrM INFORMAT10N CostiACT1 as amended (42 tf1C 2138) Sections tats, (2)%e liccusee shallreport:' *
• Scott C. Alvarez, Aar,ociate Genemt

$8 tat 9 ( 5t n (iv) Any event or condition that Counsel (202/452-a583) or Romas M. m31a,bolsa.and Arpendin Q aleoinued restJad in a manua) or automatic 202/452-3275). Cor:1, Senior Attorney (hearing impaired under ecc.102. pub. L 91-190, a3 Stat. as3 (42 actustion of any engineered safety legal Division. For the U.S C 43M). Inwns m34 and 6044 also fea ture (130), including-the reac tor only. Telecominurdcations Device for s Ismed under sec. 204. 60 Stat.1245142 UAC protection system (ItPS). except when: the Deaf (TDD), Dorothea %ompson M44) Sec00ns faLa, M91 and 6092 also (A) %c actuation resulted from and (202/45?c3544). Issued under Pub L 97-415. 96 Stot. 2073 (42 was part of a pre-planned sequence USC 22391 Section f478 also issued under 6UPPLEMENTARY INFORMATION: sec.122,66 5 tat. 933 (42 U S C,2152). Sections d.tring testing or reactor operallon: M 6N,0.81 also issued under ser-184. 68 Stat. (H) %e actuetion was invalid and*. Hodground,51 954. es amended (42 U S C n34). Appendin F (2) Occurred while the system was %c Ilank flolding Company Act of also issued under sec.187. 68 Stat. 955 (42 properly re moved from service; 1950, as 6' mended (the **UllC Act"). USC 247). (2) Occurred after the safet had been already completed;y function generally prohibits a bank holding For the pur;mnes o sec n3, sa Stat. asa, as r or company from engaging in nonbanking emended (** ULC 2m). I I f,os, so.4e(s) ' (3) Involved only the following activities or acquiring votmg securl6es and (bl. and m64(c) are inued under sec. rpecific r, gps or their equivalent of any company that is not a bank. L h l I bo6.N((I) 6 systems: Section 4(c)(a) of the UllC Act provides 2 0(e ( t(s) ena (e), f444(aHc). M 4Ns) and (b). f447(b), (i) Heactor water clean.up system: an excepdon to this prohibition where M40(a) (c). (d) and (e), f449(e). fA64(a). (i), (ii) Control room emergency the Hoard determines after notice and 010). IIHal. (pl. fql. 0). (v). and (y). 60 ss(r). ventilation s) stem: opportunity for hearing that the tassete). (cHe). (s), and (h). Loao(c). (i//) Reactor building ventilation activities being conducted are so ' moo (a),50 c24bl. 5064[b),50 65, and 50 60(a) system; closely related to banking or managing a.nd (b) are issued under sec.10lt,68 Stat. (iv) Puel building ventilation system: or controlling banks as to be a proper 949, as amended (42 U S C 22010)); and or Incident thereto."12 tl.S C.1843(c)(B). rd ) (e 6( (b t, (v) Auxiliary building ventilation The Board is authortred to make this fa70(a!. So 7tteHe) and (c), sus:(e), sa33(a) system. determination by order in an individual aed (b). m74. 50 m and 50 90 are issued case or by regulation. 'er sec.16to, ce Stat. 950 e,s amend +d (42 Deted at Hod ville,MD, this 27th day of The Board's Hegulation Y (12 CFR part ts s C art (o)). Augu st, Iw 225) set: forth a list of nonbanking Y s m.m.%_.m. -.,_,_,,_.,m ,,.,..3 ..,,,,yv.., ,,._s..... 794}}