View source for NUREG-0518, Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants

{{Adams
| number = ML20205K436
| issue date = 08/18/1986
| title = Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants
| author name = Ward D
| author affiliation = NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)
| addressee name = Zech L
| addressee affiliation = NRC COMMISSION (OCM)
| docket = 05000000, 05000206, 05000266, 05000271, 05000301, 05000374
| license number = 
| contact person = 
| case reference number = RTR-NUREG-0518, RTR-NUREG-518, RTR-REGGD-01.114, RTR-REGGD-1.114
| document report number = ACRS-SL-0325, ACRS-SL-325, NUDOCS 8704010583
| document type = MEETING MINUTES &amp; NOTES--CORRESPONDENCE, MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
| page count = 4
}}

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: ,I           ADVlsORY COMMITTEE ON REACTOR SAFEGUARDS
                   &                        WASHINGTON, D. C. 20666 August 18, 1986 Honorable Lando W. Zech, Jr.
Chairman                                                                                       '
U.S. Nuclear Regulatory Comission Washington, D.C.
20555 j

==Dear Mr. Zech:==

==SUBJECT:==
THREE HUNDRED AND SIXTEENTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, AUGUST 7-9, 1986 The Advisory Comittee on Reactor Safeguards held its 316th meeting in                          l Washington, D.C. on August 7-9, 1986.               Items considered during this meeting are sumarized below:
316th ACRS MEETING The Comittee reviewed the Proposed Standardization Policy Statement as requested by Chairman Palladino's memorandum of June 18, 1986.
The Comittee discussed its review of the issues related to the reorganiza-tion of TVA's management structure and the shutdown of TVA's nuclear power plants.
The Comittee discussed the NRC Policy Statement on Fitness for Duty of Nuclear Power Plant Personnel.
Reports on the subjects noted above have been sent to you.
The Comittee discussed the proposed revision of Regulatory Guide 1.114 Revision 2. Guidance to 0)erators at the Controls and to Senior 0)erators in the Control Room of a Nuclear Power Unit, dated June 2,1986 and tie confom-ing revisions to the Standard Review Plan Section 13.1.2.
The Committee discussed the following topics which were broached at a July 21-23, 1986 meeting of the Subcomittee on Waste Management:
: 1.      HMSS radioactive waste management program [ including the Division of Waste Management's five-year plan, the proposed Federally Funded Re-search and Development Center (FFRDC), using rulemaking to bring key issuestoclosure,andalternativemethodstoshallowlandburial].
: 2.      Programs of the Waste Management Branch, Office of Nuclear Regulatory Research.
: 3.      Generic technical positions on sorption and solubility.
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Honorable Lando W. Zech, Jr.                           August 18, 1986 I
: 4. Development of residual radiation limits for tha disposition of land, buildings, equipment, and metals resulting from the decontamination and decomissioning of nuclear power plants and fuel facilities.
: 5. Salvaging of contaminated smelted alloys,
: 6. NRC Staff policy statement and implementation of NRC policy on radioac-tive wastes "below regulatory concern."
The Committee's comments on these subjects have been provided to the Execu-tive Director for Operations. Copies have been sent to you.
The Committee met with representatives of the NRC Staff and the Seismic Qualification Utilities Group (SQUG) to discuss the seismic qualification of safety-related equipment in nuclear power plants and the proposed resolution of USI A-46. Additional discussion of this matter is planned during the 317th ACRS meeting.
l The members were briefed by representatives of the NRC Staff regarding a proposed policy statement regarding Degree Requirements for Senior Reactor
;   03erators which has been published for public coment. The members concluded t1at no ACRS action is necessary at this time.        The Comittee will keep informed regarding progress in the resolution of this matter.
l   The Comittee discussed the loss of power and water hamer event which
!   occurred at the San Onofre Nuclear Generating Station, Unit 1 on November 21,
!   1985. The Comittee concludec. that no ACR5 action is warranted regarding l   this incident.
The Comittee was briefed by representatives of the Office of Inspection and Enforcement and the Office of Nuclear Reactor Regulation regarding recent l   operating occurrences at nuclear power plants, including a feedwater tran-l   sient with partial reactor scram at the La Salle County Station, Unit 2 design deficiency involving the minimum flow recirculating valves at Ee.
point Beach Nuclear plant, Units 1 and 2, and inadequate quality control and maintenance of scram solenoid valves at the Vennont Yankee Nuclear Power Station.
l   Since the last report of ACR$ activities, the following subcomittee meetings i   have been held:
l Human Factors, in Washington. 0C, on July 15, 1986 to review: (1) 1         SECY-86-153, industry and Staff coments on proposed fitness for duty l         Policy Statement, (2) SECY-86-70, proposed rulema(ing on degree require-l         ments for SR0s at nuclear power plants, and (3) SECY-86-119, the annual
;         status report on implementation of the Commission Policy Statement on I         training and qualification Waste Manarement, in Washington, DC on July 21-23 1986, to review: (1) 17A's deve'opment (with NRC Staff's cooperation),of residual radiation limits and the disposition of land, buildings, equipment, and metals

6 Honorable Lando W. Zech, Jr.                            August 18, 1986 j         (including contaminated smelted alloys -- NUREG-0518 Final Environ-i         mental Statement) resulting from the decontamination and deconunissioning of nuclear power plants and fuel facilities; (2) the following High-Level Radioactive Waste topics being addressed by the NRC Division of Waste Management (DWM) Staff:          (a) sorption and solubility Generic Technical Positions and Draft letter Report on the Sorption Workshop, (b)  DWM's 5-y(ear (FFRDC),and              plan, (c) d) the status     the review of their NRC-proposed     Federally of DOE's Final        Funded R&D Cen Environmental l         Assessments for the candidate repository sites nominated for site l
characterizationi (3) the following subjects being investigated under
:         DWM's Low-level Radioactive Waste Program: (a) alternatives to shallow l         land burial. (b) radioactive wastes that are below regulatory concern, and (c) mixed radioactive and hazardous wastest (4) the following waste management research topics under consideration by the Office of Nuclear Regulatory Research: (a) the development of field data on the movement of radionuclides within the environment and the associated impact of heat-water-rock tory systems under  interactions, realistic(b)ield f       conditions, andthe (c)predicted performanc preview of setting priorities for waste management issues subject to rulemaking.
The Subcommittee was also briefed on DOE's Waste Isolation Pilot Plant (WIPP) in preparation for its July 29 and 30,1986 visit to that site.
* Naval Reactors (operation of a nuclear-power submarine), on July 28, 1986, to observe the activities of a nuclear submarine crew
* Westinghouse Reactor Plants, in Washington, OC, on July 30,1986 to continue the discussion and consnent on NRC Staff actions taken with respect to the 50NGS-1 water hanner/ loss of AC power event
* Scram System Reliability, in Washington, DC, on July 31,1986 to discuss the status of the ATW5 Rule implementation effort Metal Components, in Richland, WA, on August 4,1986, to review steam generator integrity program and the integrated Fracture Mechanics /
Nondestructive Examination and other PNL programs
* Reactor Operations, in Washington, DC, on August 4,1986, to review recent events at operating nuclear power plants
* Reliability Assurance, in Washington, DC, on August 5,1986, to review ThTrinal resolution of US1 A-46, " Seismic Qualification of Equipment in Operating Plants."
      '    Improv'ed LWR Desian, in Washington, DC, on August 5,1986, to discuss I
the standardization policy statement
* Extreme External Phenomena, in Washington, DC, on August 6,1986, to conduct a workshop to review the importance of seismic risk to nuclear power plants

Honorable Lando W. Zech, Jr.                                     August 18, 1986 Future Agenda The following items are tentatively scheduled for consideration during the 317th ACRS meeting September 11-13, 1986:
* Meeting with NRC Comissioners -- Discuss ACRS report dated August 12, 1986 on the proposed NRC Policy Statement on Standardized Nuclear Plants
* Proposed Revision of ECCS Requirements _ -- Proposed revision of 10 CFR 50.46, Acceptance Criteria for ECCS for LWRs and Appendix K. ECCS Evaluation Models - ACRS coments requested
* NRC Regulatory Process and Procedures -- Report of subcomittee regard-ing the IIT review of Davis-Besse loss of feedwater incident.
* Improved Light Water Reactors -- Continue discussion of proposed ACRS comments regarding characteristics of improved light water reactors
* Severe Accident Policy Plan implementation / Removal of Radioactivity from Containment Atmosphern -- ACR5 coments requested
* B&W Water Reactors -- B&W Owners Group presentation regarding reeval-uation of B&W reactors' long-term safety
* Long-Range Plan -- Continue discussion of a proposed guide for long-range planning
* Report of Maintenance Practices and Procedures Subcomittee regarding completion of Phase 1 of the NRC Maintenance and Surveillance Program Plan
* Report of Metal Components Subcomittee on NRC research activities related to primary system integrity
* Report of Subcomittee on IE Prograns regarding functional inspection of safety systems and status of the SAG program
* ReJ art of Subcomittee on Decay Heat Removal regarding Generic Issue
                                                         %-124, Auxillary Feedwater System Reliability Sincerely,
                                                                                                           ,  4 David A. Ward Chainnan
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