ML13326A647
| ML13326A647 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/07/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13326A646 | List: |
| References | |
| DPR-13-A-054 NUDOCS 8105180071 | |
| Download: ML13326A647 (18) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206.
SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 54 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The applicationsfor amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated August 27, 1980, and February 2, 1981, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission s regulations and all applicable requirements have been satisfied.
810518 071
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No. DPR-13 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Dennis M. Crutchfield, C ef Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 7, 1981
ATTACHMENT TO LICENSE AMENDMENT NO. 54 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications and Bases and Appendix B Technical Specifications by-removing the following pages and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the areas of change.
PAGES*
Appendix A 69 70 70a 72a 73 74 75 79 Appendix B 5-1 5-2 5-3 5-4 5-5
- Pages 45 and 46c are included to clarify the primary and secondary enumeration of Section 4.2,.which is necessary as a result of Technical Specification provisions issued by NRC Order dated April 20, 198-1.
4.2 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEM 4.2.1 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEM PERIODIC TESTING Applicability Applies to testing of the Safety Injection System and the Containment Spray System.
Objective:
To' verify that the Safety Injection System and the Con tainment Spray System will respond promptly and properly if required.
Specification:
I. System Test A. Safety Injection System (1) Durina reactor shutdown at intervals not longer than the normal plant refueline intervals, a "no-flow" system test shall be conducted to demonstrate proper availability of the system. The test shall be performed in accordance with the following procedure:
(a) The feedwater, safety injection, charging, condensate, and heater drain pumps shall not be operating. Their respective breakers shall be racked-out to the test position with control powor available.
(b) The flow path for condensate shall be positively blocked prior to the test.
(c) Injection and recirculation system operation shall be initiated by instrumentation and controls installed in the control room.
(2) The test will be considered satisfactory if control board indication and visual observa tions indicate all components have operated and sequenced properly. That is, the appropriate pump breakers have opened and closed, and all valves have completed their travel.
(3) A test of the trisodium phosphate additive shall be conducted to demonstrate the availability of the system. The test shall be performed in accordance with the following procedure:
(a) The three (3) storage racks are visually observed to have maintained their integrity.
(b) The three (3) racks, each with a storage capacity of 1800 pounds of anhydrous trisodium phosphate additive, are visually observed to be full.
0C 4:2.2 Primary Coolant System Pressure Isolation Valves Testing (Surveillance Requirement)
Applicability Operational Modes 1, 2, 3 (Power Operation, Startup, and Hot Shutdown) applies to the operational status of the primary coolant system pressure isolation valves.
Objective:
To increase the reliobility of primary coolant system pressure isolation valves thereby reducing the potential of an inter system loss of coolant accident.
Specification:
(a)
- 1. Periodic leakage testing on each valve listed in Table 3.3.4-1 shall be accomplished every time the plant is placed in the cold shutdown condition for refueling, each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the pre ceeding 9 months, and prior to returning the valve to service after maintenance, repair or replacement work is performed.
To satisfy ALARA requirements, leakage may be measured indirectly (as from the performanLe of pressure indicators) if accomplished in accordance with approved procedures and supported by computa tions showing that the method is capable of demonstratina valve complia~nce with the leakage criteria.
The minimum.test differential pressure shall not be less than 150 psid MC Order dated: April 20,. 1981 Amendment No. 54
CHAIRM4AN OF THE BOARD SENIOR VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICEPRESIDENT NU7LEAR (FUEL SUPPLY)
(NUCLEAR ENGINEERING (POWER SUPPLY)
(SYSTEM (ENGINEERING &
(ADVANCED CONTROL AND OPERATIONS)
DEVELOPMENT)
CONSTRUCTION)
ENGINEERING)
BOARD NU)LEAR AUDIT AND REVIEW COMMITTEE MANAGER OF MANAGER OF MANAGER OF MANAGER OF NUCLEAR ENGINEERING, NUCLEAR ENVIRONMENTAL ENGINEERING SAFETY & LICENSING OPERATIONS AFFAIRS DESIGN DIRECTOR OF
- MANAGER, RESEARCH AND QUALITY DEVELOPMENT ASSURANCE PROJECT MANAGER MANAGER, NUCLEAR TRAINING
- MANAGER, SAN ONOFRE UNIT 1 ENGINEERING &
MANAGER BIOLOGICAL RETROFIT PROJECTS SAFETY SYSTEMS R&D HEADQUARTERS STAFF STATION STAFF STATION ON-SITE MANAGER REVIEW COMMITTEE 6.2.1.1 OFFSITE ORGANIZATION S69..
Amendment No.
$0 g0, 54
FIGURE 6.2.2.2 Station Manager Asst. Station Asst.' Station Asst. Station HeaIth Physics Station Manager Manager Manager Manager Services Operations Maintenance Technical Manager Supervisor of Supervisor of Supervising Health Physics Administratior Station Security Plant Maintenance, 501 Engineer, I&C Supervisor, 501 Supervisor III Plant1 Maintenance Supervisor of Plant Foremen, 501 Industrial Superintendent, SOI Foremen, SO Instrumentation, SO J
Safety & Fire IITechnicians, 501 Protection Maintenance Foremen, 501 Supervisor Watch*
Supervisor of Personnel, 501 1Radwaste Engineers, Plant Technici 01 pervi S011 Coordination, 501I I
I Chemistry Supervisor Technicians Operating*
Operating I
Foremen, SU1 Foremen, S01 Foremen Dosimetry I
Supervisor TechniciansI Plant**
Foremen Operators, S0a Compliance Engineer ALARA Supervising Engineers Engineer Engineers Shift Technical Advisors, SOo SAt time of appointment to the position, SeniIor Reactor Operator License Required TSenior Reactor Operator License Required Control and Assistant Control
-perators are holders of ReactorOperator Licenses r 70 enendent No.
54
SENIOR VICE PRESIDENT VICE PRESIDENT VICE RESIDENT POWER SUPPLY DEPARTMENT NUCLEAR ENGINEERING & OPERATIONS MANAGER, POWER CORPORATE FIRE SUPPLY SERVICES PREVENTION COMMITTEE ADMINISTRATOR POWER SUPPLY SERVICES FIRE CONTROL AND MANAGER OF CONSERVATION NUCLEAR OPERATIONS REPRESENTATIVE FIRE CONTROL CONSULTANT HEADQUARTERS FIELD STATION MANAGER FIRE EQUIPMENT ASST. STATION ASST. STATION STATION INSPECTORS MANAGER MANAGER SERVICES OPERATIONS MAINTENANCE MANAGER PLANT SUPERVISOR INDUSTRIAL SAFETY SUPERINTENDENT, S01 OF PLANT
& FIRE PROTECTION MAINTENANCE, S01 SUPERVISOR PLA T FIRE BRIGADE, 501 STATION FIRE COMMITTEE FIGURE 6.2.3.1 FIRE PROTECTION STAFF AND LINE ORGANIZATIONS 70a -
Amendment No. 37, #7, 50,54
- 72a
- 6.3 Facility Staff QualI fi cation 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, "Selection and Training of Personnel for Nuclear Power Plants," for comparable positions. The Health Physics Manager shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, September, 1975."
6.4 Training 6.4.1 A retraining and replacement training program for the faciity staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction bf the Training Manager and shall meet or exceed the requirements of Section 27 of the National Fire Protection Association Code - 1976."
Amendment No. $7,, 54
6.5 REVIEW AND AUDIT 6.5.1 ONSITE REVIEW COM1MITTEE (OSRC)
FUNCTION
-6.5.1.1 The OSRC shall function to advise the Station I
Manager on all matters related to nuclear safety.
COMPOSI"TO; "6,5.1.2 The OSRC shall be composed of the:
Chairman:
Station Manager.
Member:
Assistant Station Manager, Operations Member:
Assistant Station Manager, Technical Member:
Plant Superintendent, S01 Member:
Supervising Engineer, I&C Member:
Health Physics Manager Member:
Chemistry Supervisor Member:
Assistanttation Manager, Maintenance Member:
Engineer ALTERNATES Member:
San Diego Gas & Electric Representative 6.5.1.3 Alternate emSers shall be appointed in writing by the OSRC Chairvan to serve on aitenporary basis; however, no more than two asernaes shll participate inOSRC activities at any one time.
MEETING TREQUENCY 6.5.1.4 The OSRC shall meet at least once per calender month andas convened by the OSRC Chairman.
QUORUM "6.5.1.5 A quorum of the OSRC shall consist of the Chairman or his designated alternate and three members, including alternates."
RESPONSIB1LITIES 6.5.1.6 In perforrhiy their duties with regard to these Appendix A Techn:ical Specifications, the OSRC shall be responsible for:
- a. Review of 1) all procedures required by Specifi cation 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety.
- b. Review of all prcposed tests and experiments that affect nuclear safety.
Amendment No.--39, #Z, 54
- c.
Review of all.proposed changes to the Technical Specifications.
- d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
- e.
Investigation of all violations of the Technical Specifications and preparation and forwarding of a report covering evaluation and recommendations to prevent recurrence to the Manager of Nuclear Operations and to the Chairman of the Nuclear Audit and Review Committee."
- f. Review of facility operations to detect potential safety hazards.
- g. Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Audit and Review Coumittee.
- h. Review of the Plant Security Plan and implementation procedures at least once each two years.
- i. Review of the Emergency Plan and implementing pro cedures and shall submit recommended changes to the Chairman of the Nuclear Audit and Review Committee.
AUTHORITY 6.5.1.7 The OSRC shall:
- a. Recommend to the Station Manager written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
- b. Render determinations to the Station Manager in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above con stitutes an urreviewed safety ouestion.
- c.
Provide immediate written notification to the Manager of Nuluear Operations and the Chairman of Nuclear Audit and Review Committee of disagreement between the OSRC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such aisagreements pursuant to 6.1.1 above."
Amendment No., 3, 54
-75 RE CORDS "6. 5.1.8. The OSPC shall maintain wr iIt t en minutes o f each meeting anc copies shall be provided to. the Manager of Nuclear Operations, a -)a, mairn of the Nuclear Audi" and ReviewCbite.
- 6. 5.2 NUC1.El AL 7 k\\,) R-c T
7C.
z.:' (N A:C)
F UNCI. 11 6.5.2. 1 The NXRC Provides indepe-ndei~t -review and audit of desliniatcd activi:'.es i n thc area of ruclear safety (sce Ap-endix A, N R - 12) anid erivi ron.en ta 1 izpacc (see Ap pen d ix B~, DPR-J3).
"16.5.2.2 The-NARC shall be composed of the:
Manager of. Engineering Des in
- Manacer-of Envirdnmental Affairs Manacer-o f Nuclear Eigineering, Safecy &Licensing.
Manacer, Quality Assur.arce manager of Nuclear Operations Manager, Nuclear Egirneering & Safety
.Manage,,
Biological Syst~ems'Researrzh Dn evelcpfrent
- San;Diego Gas. Electric Representative Chairmash. L s.- al11 t e cesi gt-a tec. :y thj-e Nuclear Control Scaro.
6.5.2.3 Al e ate me=_ber ts 1-1 d I be avP o int e d in wri t ing by t he AR C C ha ia 7 to s crve. on,a t c-. po a -y basis ; hc,-wev e r no more tha wto a,:er-ates shall par"icipate in, NARC Aci:Pv tie 3 a, any an '=e.
CON S UI N7.
6.5. 2.4'r Cn at-s h a II be ut 1 1zed as de-lr~ned by the NARO C "4,i
- a n
?s F IC G F':"'
6.15.2. 5 7The. NA RC h a 1 rt e
-a: eas t once per i x nthr.
Amendment No.
,0 5
79
- b. Review-and approve recommended changes to the Technical Specifications.
- c. Submit proposed changes to the Technical Specifications to the Commission.
- d. Maintain management control with respect to nuclear safety.
6.6 DELETED 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety L'imit is violated:
- a. The provisions of 10 CFR 50.36 (c)(1)(i) shall be complied with immediately.
- b. The Safety Limit violation shall be reported to the Commission, the Manager of Nuclear Operations and to the NARC Chairman immediately."
- c. A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the OSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
- d.
The Safety Limit Violation Report shall be submitted to the Commission, the NARC and the Manager of Nuclear Operations, within 14 days ofthe violation."
6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be established, implemnted'and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1976, Administrative Controls for Nuclear Power Plants; Appendix "A" of USNRC Regulatory Guide 1.33, Rev. 1, Quality Assurance Program Requirements (Operation); and Paragraph 2.2.1 of Fire Protection Proram Review, STP APCS8 9.5-1, San Onofre Nuclear Generatinc Staion, Unit 1.
March, 19i/; except as proviaed in 6.8.2 and 6.8.3 below.
6.8.2 Each procedure and administrative policy of 6.8.1 above and changes thereto sha11 b.e reviewed by thet 0SRC and app the Station Manager prior to implemen tation.
Amendment No.
SJ, p,
54
0 Responsibility The Southern California Edison Company shall be solely responsible for the operation.of San Onofra Nuclear Generating Station Unit 1. Xanage ment responsibility at.th'e station and corporate levels shall be as specified in Section 5.3:
and shall ensure that these environmental technical specifications are fullyir.plemented and that continued pro tection to the environment shall be provided at all times. Responsibility shall be exercised at the corporate level to provide that the group, individual or organization assigned to audit or otherwise verify that an activity has been correctly performed is independent of the individual, group or organization direcrly responsible for performing the specific activity. Where other orgamizations are delegated responsibility for executing portions of these environmental technical specifications, the Southern California Edison Cc=-pany shall retain responsibility for all such activities. A detailed description of the program utilized to audit or otherwise verify thar an activity has been correctly perfor-ed shall be developed and sub-i:ted to the Directorate of Licensitg for review within 4.months of the effective date of these environmental technical specifications. The audit and verification program.shall be established awd conducted in accordance with this program description.
5.2 Organization 5.2.1 The corporate organization, which provides the line responsibility for the operation of the Sta:io and the staff responsibilities in support of these operations, is depicted in Figure 5.2-1.
5.2.2 The Station organization utilized in the operation and maintena::e of the Station is depicted I: ?igure 5.2-2.
"5.2.3 The Health Physics Manager and the Chemistry Supervisor shall be the Onsite Review Comittee members responsible for environmental issues. These members shall be qualified in environmental matters."
5.3 Review and Audit Review and audit of Station onerations shall be provided by the Onsite Review Coitee the Nuclear Audit and Review Committee, the 'iuclear
- mmite, th Nuclea Control Board-and the Quality Assurance Organization.
5.3.1 The menbership of the Onsite.eview Cowittee and the responsibilities and authorities of the Co ittee with respect to these environmental technical specif~eations azk as follows:
- a. Membership (1)
Station Manager (Chairman)
(2)
Assistant Station Manager, Operations (3)
Assistant Station Manager, Technical (4)
Plant Superintendent, SOI (5)
Supervising Engineer, I&C (6)
Health Physics Manager (7)
Chemistry Supervisor (8)
Assistant Station Manager, Maintenance (9)
Engineer (10)
San Diego Gas & Electric Representative 5-1 Amendment No.
54
CHAIRMAN THE BOARD SENIOR VICE RESIDENT VICE PRESIDENT VICE PRE IDENT VICE PRESIDENT VICE PkESIDENT VICE PRESIDENT VICE PRESIDENT NUCLEAR (FUEL SUPPLY)
(NUCLEAR ENGINEERING (POWER SUPPLY)
(SYSTEM (ENGINEERING &
(ADVANCED CONTROL AND OPERATIONS)
DEVELOPMENT)
CONST UCTION)
ENGINEERING)
BOARD NUCLEAR AUDITAN REVIEW COMMITTE MANAGER OF MANAGER OF MANAGER OF MANAGER OF NUCLEAR ENGINEERING, NUCLEAR ENVIRONMENTAL ENGINEERING SAFETY & LICENSING OPERATIONS AFFAIRS DESIGN DIRECTOR OF
- MANAGER, RESEARCH AND QUALITY DEVELOPMENT ASSURANCE PROJECT MANAGER MANAGER, NUCLEAR TRAINING
- MANAGER, SAN ONOFRE UNIT 1 ENGINEERING &
MANAGER BIOLOGICAL RETROFIT PROJECTS SAFETY SYSTEMS R&D HEADQUARTERS STAFF STATI'ON STAFF STATION ON-SITE MANAGER REVIEW COMMITTE FIGURE 5.2-1 SOUTHERN CALIFORNIA EDISON COMPANY CORPORATE ORGANIZATION 5-2 Amendment No. 39.
$0, 54
Station Manager Asst. Station Asst. Station Asst. staton eatth Physics Station Manager Manager Manager Manager Services Operations Maintenance Technical Manaqer Supervisor of Supervisor of Supervising Health Physics Administration Station Security P1ant Maintenance, SG0 Engineer, 1&C Supervisor, S01 K Supervisor Plant1 Maintenance Supervisor of Plant Foremen, SO1 Industrial Superintendent, Sl
- Foremen, 501 Instrumentat ion, Sol ILSafety
& Fire Technicians, Sl Protection Mai ntenance Foremen, Sol Supervisor Watch*
Supervisor of Personnel, 501 Radwaste Engineers, Plant Technicians, Sl Supervisor Sol Coordination, 501 Chemistry Supervisor Technicians Operating*
Operating Foremen, SUl Foremen, SO1 Foremen Dosimetry Supervisor Techn clans Pl nt**
Foremen operators 501
-Compliance Engineer ALARA Supervising Engineers Engineer Engineers Shift Technical.
Advisors, Sol FIGURE 5 2-2 SAN ONOFRE NUCIEAR GENRATING STATION (LNIT 1) ORGANIZATION At time of appointment to the position, Senior Reactor Operator License Required Senior Reactor Operator License Required Control and Assistant Control Operators are holders of Reactor Uperator Licenses 5-3 Amendment No.
54
0
- b.
Responsibilities and Authority (1) Determine potential environmental hazards by review and evaluation of facility activities (2)
Analyze and review Environmental Technical Specification viola;ions.
Submit reports of such incidents to the Nuclear Audit and Review Committee.
(3) Analyze and review reportable environmental occurrences or other facility incidents which relate to the environmental impact of the station and its operation. Submit reports of such incidents to the Nuclear Audit and Review Committee.
(4) Review and approve facility procedures, tests or experiments and changes thereto which relate to the environmental impact of the station and its operation.
(5) Review and approve proposed changes to the facility which relate to the environmental impact of the station and its operation.
(6) When items reviewed under paragraphs (4) and (5) above involve a change in the Environmental Technical Speci fications, or a change which would significantly alter the environmental impact of the facility, it shall be submitted to the Nuclear Audit and Review Committee.
(7) Review proposed changes to the Environmental Technical Specifications and submit to the Nuclear Audit and Review Committee.
(8) Review station-based environmental surveillance programs for compliance with these environmental technical specifications.
- c. Meeting Frequency: Monthly and as Required A. Quorum:
The Chairman or his designated alternate plus three members, including alternates. For environmental matters, either the Health Physics Manager or the Chemistry Supervisor or the respective designated alternate shall be oresent.
- e.
Alternates:
Alternate members shall be appointed in writing by The Onsite Review Committee Chairman to serve on a temporary basis; however, no more than two alternates shall participate in Onsite Review Committee actions at any time.
Amendment No. $,
54
3.2 The membership of the Nuclear Audit and Review Comittee andth@
U2pntbltS an uhrties of the Comittee with respect to
- eposiilte fan h Ad tR h
these enviremntal technical specifications are as follows:
- a.
Me hip (Chairman designated by the Nuclear Control Board)
(1)
Manager of Engineering Design (2)
Manager of Environmental Affairs (3) Manager of Nuclear Engineering, Safety & Licensing (4) Manager, Nuclear Engineering & Safety (5)
Manager, Biological Systems Research and Development (6) Manager, Quality Assurance (7) Manager of Nuclear Operations (8) San Diego Gas & Electric Representative"
- b.
Responsibilities (1) Review and investigate reports concerning violations of the Environmental Technical Specifications. Where invest igtion indicates, evaluate and prepare recommends tions to prevent their recurrence.
(2) Review proposed changes to the Environmental Technical Specifications. Coordinate environmental technical specifications5 with the safety technical specifications to avoid conflicts and maintain consistency.
Submit approved proposed changes to the Environmental Technical Specifications to the Nuclear Control Board for transmittal.
(3) Review and approve proposed changes to the facility and its procedures or proposed tests or experiments which are forwarded by the onsite Review Committee when they involve a change in the Environmental Technical Specifications or a change which would significantly alter the environmental impact of the facility.
Submit such proposed changes when required with appropriate environmental analysis to the Nuclear Control Board for transmittal.
(4) Review all environmental surveillance programs for compliance with these environmental technical specifications.
(5) Review all design'changes related to changes in the Station which relate to the environmental impact of the station and its operation.
(6) Review overall facility activities as they relate to environmental impact by:
(a) formal facility review annually and as directed by the Committee Chairman.
Amendment No. 390 50, 54 5-5