ML20011D780
| ML20011D780 | |
| Person / Time | |
|---|---|
| Issue date: | 12/11/1989 |
| From: | Michelson C Advisory Committee on Reactor Safeguards |
| To: | Carr K NRC COMMISSION (OCM) |
| References | |
| TASK-087, TASK-OR ACRS-SL-0364, GL-88-20, NUDOCS 8912290081 | |
| Download: ML20011D780 (6) | |
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8 NUCLEAR REGULATORY COMMISSION
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' ADVISORY COMMITTEE ON REACTOM SAFEGUARDS I
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December 11, 1989 N
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The Honorable Kenneth M. Carr Chairman
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Dear Chairman Carr:
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SUBJECT:
SUMMARY
REPORT - THREE HUNDRED FIFTY-FIFTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, NOVEMBER 16-18, 1989 During its 355th meeting, November 16-18, 1989, the Committee i
completed the activities noted below and prepared the following reports and letters.
Copies of these reports and letters have been provided to you:
t REPORTS TO THE COMMISSION o
Draf t ' Sunnlement No.
2 to Generic Letter 88-20.
" Accident Manaaement Strateales for Consideration in the Individual Plant Examination Process" (Report to Chairman carr, dated November 20, 1989) o Proposed Resolution of Generic Issue 87.
"HPCI - Steam Line Break Without Isolation" (Report to Chairman Carr, dated November 20, 1989) o ADDointment of ACRS Members (Report to Chairman Carr, dated November 20, 1989) o Examnle of NRC Emoloyees Inventiner or Innosina New Reauirements (Letter to Chairman Carr, dated November 20, 1989)
Coherence in the Reaulatory Process (ReDort to Chairman Carr, o.
dated. November 24, 1989)
LETTERS TO THE ACTING EDO a
o Relationshio of the Ouantitative Safety Goal to the Concept of Adecuate ProtectioD (Letter to J.
Taylor, dated November 20, 1989)
DESIGNATED ORIGINAL cerunoa 3, [yg l
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o The Honorable Kenneth M. Carr 2
December 11, 1989 o
Module 1 of the Draft Safety Evaluation Report for the Advanced Boilina Water Reactor Desion (Letter to J. Taylor, dated November 24, 1989)
OTHER ACTIONS. AGREEMENTS. ASSIGNMENTS. AND REOUESTS o
Hine Mile Point Unit 1 Restart The Ccamittee decided to continue its review of the restart of Nine Mile Point Unit i subsequent to the staff's approval of the restart.
Since the committee's review may take place during the startup phase, the Committee decided that there is no need to delay the restart of the plant.
(See memorandum from R. Fraley for J. Taylor, dated November 24, 1989.)
o Proposed 10 CFR Part 55. Operators' Licenses The Committee decided to review the proposed revision of 10 CFR Part 55 to require compliance with fitness for duty programs and conforming modifications to the Commission's enforcement policy.
(Memorandum from R.
Fraley for J.
Roe dated November 24, 1989) o NUMARC/NUPLEX Industry License Renewal Toolcal Reports The Committee decided that the ACRS should be given an opportunity to review and comment on the industry topice.1 reports related to license renewal that are being prepared by k
Some of these reports have already been prepared and submitted to the NRC staff for review. The NRC staff has been requested to provide copies of these reports to_the ACRS and their evaluation of these reports when they are available.
(See memorandum from R. Fraley for T. Murley, dated December 5, 1989.)
o ACRS/ACNW Resoonsibilities The Committee acknowledged the division of responsibilities between the ACRS and the ACNW specified by the commission in l
the memorandum from Chairman Carr dated November 6, 1989, and discussed mechanisms to provide for joint input in areas of mutual interest.
o Standardized Advanced LWRs t
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The NRC staff briefod the Committee regarding the status of l
its review of the following evolutionary and advanced light water reactor designs:
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i The Honorable Kenneth M. Carr 3
' December 11, 1989 l
1 Westinghouse WAPWR SP/90 Westinghouse AP 600 Combustion Engineering System 80+
1 The tentative schedule proposed by the staff for the ACRS full j
committee consideration of these designs is given below:
Westinghouse WAPWR SP/90 (PDA)
- April 1990 Westinghouse AP 000
- April 1990 (Initial discussion)
Combustion Engineering System 80+ - February 1990 (Licensing Review Basis Document) l o
Three Mile Island Nuclear Station Unit 2 The NRC staff briefed the Committee regarding the status of the recovery efforts, including the investigation of the reactor vessel lower head indications at TMI-2.
o ACRS Meetina Dates for Calendar Year 1990 l
t The' Committee approved the following meeting dates for calendar year 1990:-
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357th Meeting January 11-13, 1990 358th Meeting February 8-10, 1990 359th Meeting March 8-10, 1990 360th Meeting April 5-7, 1990 361st Meeting May 10-32, 1990 362nd Meeting June 7-9, 1990 363rd Meeting July 12-14, 1990 364th Meeting August 9-11, 1990 365th Meeting September 6-8, 1990 366th Meeting October 4-6, 1990 367th Meeting November 8-10, 1990 368th Meeting December 6-8, 1990 (The June 1990 meeting dates may change to accommodate the Second International Conference of Advisory Committees.)
o Meetina with the commission The Committee proposed a meeting with the Commissioners during the 356th ACRS meeting, December 14-15, 1989.
Items tentatively scheduled for discussion are:
Status of ACRS activities related to the development of containment design criteria for future plants.
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The Honorable Kenneth M. Carr 4
December 11, 1989 1
1 NRC Safety Research Program budget (Tentative)
" Management" of Licensee activities by NRC Regional Staff.
l (This meeting has been deferred to January 1990.)
SUBCOMMITTEE MEETINGS j
Since the last report of ACRS activities, the following subcommittee meetings have been held:
o Joint Containment Systems and Structural Encineering, October 17, 1989 The Subcommittees discussed containment design criteria for future plants with
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invited speakers from the industry and national laboratories.
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Adyanced Boilina Water Reactors (GE ABWR), October 31, 1989 - The Subcommittee reviewed the NRC staff's Draft Safety Evaluation Report related to Module 1 of GE ABWR.
o Advanced Pressurized Water Reactors, November 3, 1989 -
The Subcommittee discussed. the Westinghoure Advanced Pressurized Water Reactor Design (RESAR-SP/90).
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Thermal-Hydraulic Phenomena, November 8-9, 1989 - The Subcommittee discussed the capability of the thermal-hydraulic codes to model BWR core power instability, and the key thermal-hydraulic design aspects of the GE ABWR related to the ECCS and LOCA analyses.
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Thermal-Hydraulic Phenomena, November 14, 1989 The Subcommittee discussed selected portions of the NRC thermal-hydraulic research program, including future research needs in this area and the recent ACRS report commenting on thermal-hydraulic research.
General Electric Reactor Plants, November 14, 1989 - The o
Subcommittee reviewed the restart of Nine Mile Point Unit 1.
o Reaulatory Policies and Practices, November 15, 1989 L
The Subcommittee continued its discussion on the integration of the regulatory process.
o Thermal-Hydraulic Phenomena, December 7,
1989 The Subcommittee discussed:
programs for the resolution of the issue on Interfacing I.
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o The Honorable Kenneth M. Carr 5
December 11, 1989 f
Systems LOCA; the status of the RES' Technical Program Group's efforts to apply the Code Scaling, Applicability, and Uncertainty (CSAU) evaluation methodology to t
calculation of a small-break LOCA; and the status of development of the Westinghouse best-estimate ECCS/LOCA model.
EEECIAL MEETING o
ACRS Meetina with the Canadian Advisory Committee on Nuclear Safety, November 1-2, 1989 - The Committees discussed several safety-related matters applicable to nuclear power plants including institutional quality assurance and
- attitude, nuclear power plant personnel selection and training, severe accident analysis, and containment performance criteria.
SCHEDULE FOR THE 356TH MEETING The Committee agreed to the following tentative schedule for the 356th ACRS meeting, December 14-15, 1989:
Nuclear Power Plant Access Authorization - Review and report o
on proposed final rule on Personnel Access Authorization Requirements for Nuclear Power Plants (10 CFR Part 73.56).
o Containment Performance Imorovement Proaram Review and report on proposed NRC. program to improve containment performance during severe accident conditions for all containment types except Mark I containment.
Technical Trainina and Oualification Procram for NRC Ecoloyees o
Briefing by NRC staff representatives regarding training courses at the NRC Technical Training Center at Chattanooga, TN.
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Fitness for Duty - Review and report on proposed revision of 10 CFR Part 55 to require operator compliance with NRC fitness-for-duty programs and conforming modification to the Commission's enforcement policy.
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o Meetina with Actina EDO Discussion regarding lack of coherence in the NRC regulatory process.
o ACRS Subcommittee Activities - Hear and discuss reports of ACRS Subcommittees regarding the status of assigned activities regarding safety-related matters, including the activities related to thermal hydraulic phenomena, etc.
t The Honorable Kenneth M. Carr 6
December 11, 1989 o
Evaluation of Operational Date Briefing and discussion regarding use of SALP ratings in the regulatory process and elsewhere, o
Meetina with the commissioners - Discussion of the following items:
Status of ACRS activities related to the development of 1.,
containment design criteria for future plants NRC Safety Research Program budget (Tentative)
" Management" of Licensee activities by NRC Regional staff.
(This meeting has been deferred to January 1990.)
Sincerely, Carlyle Michelson Acting Chairman i
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