ML20195E267
| ML20195E267 | |
| Person / Time | |
|---|---|
| Issue date: | 06/07/1988 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Stello V NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-0933, RTR-NUREG-737, RTR-NUREG-933, TASK-***, TASK-1.A.1.1, TASK-1.A.2.2, TASK-1.A.2.6, TASK-1.A.4.2, TASK-2.E.6, TASK-OR, TASK-TM ACRS-R-1310, IEB-85-003, IEB-85-3, NUDOCS 8806230341 | |
| Download: ML20195E267 (11) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION g
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- j ADVISORY COMMITTEE ON 3EAcTOR SAFEGUARDS q
wAssiNorow. o. c. 20sss June 7, 1988 MEMORANDUM FOR:
Victor Stello, Jr.
Executive Director for Operations FROM:
R
..o F. Fraley Executive Director, ACRS
SUBJECT:
PROPOSED PRIORITY RANKINGS OF GENERIC ISSUES:
FIFTH GROUP During the 338th meeting of the Advisory Comittee on Reactor Safeguards, June 2-4, 1988, the members reviewed the adequacy of the proposed priority rankings for a group of Generic Issues identified in the attached Table A, and their coments are contained in the following attachments.
- Attachment I lists those issues for which the ACRS agrees with the priority rankings proposed by the NRC Staff.
- Attachment 2 includes those issues for which the ACRS agrees with the priority rankings proposed by the NRC Staff, but has coments.
- Attachment 3 identifies the Generic Issue for which the ACRS disagrees with the NRC Staff's proposed priority ranking along with the reasons therefor.
The members have requested that the NRC Staff provide written responses to the coments identified in Attachments 2 and 3.
The ACRS will continue its review of the adequacy of the proposed priority rankings for additional Generic Issues when they become avail-able.
Attachments: As Stated 8806230341 000607 PDR ACHS PDR R-1310
O TABLE A GENERIC ISSUES REVIEWED BY THE ACRS DURING THE 338TH, JUNE 2-4, 1988, MEETING GENERIC PRIORITY RANKING ISSUE TITLE PROPOSED BY THE REFERENCE NUMBER NRC STAFF DOCUMENT 88 Earthquakes and Emergency RESOLVED Memorandum from Planning E.S. Beckjord, dated October 6, 1987 106 Piping and the Use of MEDIUM Memorandum from Highly Combustible Gases E.S. Beckjord, dated in Vital Areas November 3, 1987 113 Dynamic Qualification HIGH Memorandum from Testing of Large Bore E.S. Beckjord, dated Hydraulic Snubbers July 2, 1987 125 Davis-Besse loss of All Feedwater Event of June 9, 1985 - Long-Term Actions 125.1.1 Availability of the Shift DROP Memorandum from Technical Advisor (Thesafetyconcern E.S. Beckjord, dated of this !ssue has July 2, 1987 been addressed by licensees in response to TMI Action Plan Item I.A.1.1, "Shift Technical Advisor")
125.I.3 SPDS Availability MEDIUM Memorandum from E.S. Beckjord, dated May 6, 1988
Table A (Cont'd) GENERIC PRIORITY RANKING ISSUE TITLE PROPOSED BY THE REFERENCE NUMBER NRC STAFF DOCUMENT 125.I.4 Plant Specific Simulator DROP Memorandum from (Thesafetyconcern H.R. Denton, dated of this Issue has February 20, 1987 been addressed in the resolution of TMI Action Plan ItemI.A.4.2(4),
"Review Simulators for Confonnance to Criteria")
125.I.6 Valve Torque Limit and DROP Memorandum from Bypass Switch Settings (The safety concern E.S. Beckjord, dated of this Issue has December 31, 1987 been addressed by licensees in response to IE Bulletin 85-03 and by the Staff in the resolution of TMI Action Plan Item II.E.6.1, "Test Adequacy Study")
125.I.7.a-Recover Failed Equipment DROP Memorandum from (The safety concern E.S. Beckjord, dated of this Issue has December 31, 1987 been addressed in the resolution of TMI Action Plan Items I.A.2.2, "Training and Quali-fication of Opera-tions Personnel,"
andI.A.2.6(5),
"Develop Inspection Procedures for Train-ing Program " and Human Factors Issue HF 2.1, "Evaluate IndustryTraining")
L l
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Table A (Cont'd).
GENERIC PRIORITY RANKING ISSUE TITLE PROPOSED BY THE REFERENCE NUMBER NRC STAFF DOCUMENT 125.I.7.b Realistic Hands-on DROP Memorandum from Training (The safety concern H.R. Denton, dated of this Issue is March 10, 1987 being addressed by the Policy Statement on Training and Qualifications,and by the work related to the resolution of Human Factors Issue HF 3.1, "Develop Job Knowledge Catalog")
125.i.8 Procedures and Staffing DROP Memorandum from for Reporting to NRC (Thesafetyconcern E.S. Beckjord, dated Emergency Response Center of this issue has June 3, 1987 been addressed in the resolution of TMI Action Plan Item III.A.3.4, "Nuclear Data Link")
125.11.1 Need for Additional Actions on AFW Systems 125.II.1.a Two-Train AFW Unavail-DROP Memorandum from ability (The safet; concern H.R. Denton, dated of this issue has Octuber 8, 1986 been addressed in the resolution of Generic Issue 124, "Auxiliary Feed-water System Reli-ability")
125.II.1.b Review Existing AFW HIGH Memorandum from Systems for Single H.R. Denton, dated Failures October 8, 1986
Table A (Cont'd)
-4 GENERIC PRIORITY RANKING ISSUE TITLE PROPOSED BY THE REFERENCE NUMBER NRC STAFF DOCUMENT 125.II.1.c NUREG-0737 Reliability DROP Memorandum from Improvements H.R. Denton, dated October 8, 1986 125.II.1.d AFW Steam and Feedwater DROP Memorandum from Rupture Control System /
(Thesafetyconcern H.R. Denton, dated ICS Interactions in B&W of this Issue has October 8, 1986 Plants been addressed in the resolution of GenericIssue124) 125.11.2 Assess the Adequacy of DROP Memorandum from Existing Maintenance (The safety concern E.S. Beckjord, dated Requirements and Their of this issue has June 11, 1987 Impact on the Resulting been addressed in Reliability of Safety-the resolution of Related Systems Human Factors Issue HF 8. "Maintenance and Surveillance Program")
125.11.5 Thermal-Hydraulic Effects DROP Memorandum from of Loss and Restoration (This safety concern E.S. Beckjord, dated of Feedwater on Primary of this Issue has June 17, 1987 System Components been addressed in the resolution of USI A-49, "Pres-surized Thermal Shock")
125.11.6 Reexamine PRA-based DROP Memorandum from Estimates of the Likeli-(The safety concern H.R. Denton, dated hood of a Severe Core of this Issue has March 26, 1987 Damage Accident Based been addresed in the on Loss of All Feedwater resolution of USI A-45, "Shutdown Decay Heat Removal Requirements," and Generic Issue 124) l l
Table A (Cont'd)
-S-GENERIC PRIORITY RANKING ISSUE TITLE PROPOSED BY THE REFERENCE NUMBER NRC STAFF DOCUMENT 125.11.8 Reassess Criteria for DROP Memorandum from Feed-and-Bleed Initiation (The safety concern H.R. Denton, dated of this Issue has March 26, 1987 been addressed in the resolution of Generic Issue 122.2, "Initi-ating Feed-and-Bleed")
125.11.10 Hie,archy of Impromptu DROP Memorandum from Operator Actions (The safety concern H.R. Denton, dated of this Issue has February 21, 1987 been addressed in the resolution of Human Factors Issue HF 4.4, "Guidelines for Upgrading Other Procedures")
125.11.12 Adequacy of Training DROP Memorandum from Regarding PORY Operation (The safety concern H.R. Denton, dated of this Issue has March 10, 1987 been addressed in ths resolution of Human Factors Issue HF 3.1, "Develop Job Knowledge Catalog")
125.11.13 Operator Job Aids DROP Memorandum from (The safety concern E.S. Beckjord, dated of this Issue has March 1, 1988 been addressed by the INP0 Training Accreditation Pro-gram which was endorsed in March 1985 by the Com-mission Policy Statement on Train-ing and Qualifica-tion of Nuclear Power Plant Person-nel)
TableA(Cont'd) GENERIC PRIORITY RANKING ISSUE TITLE PROPOSED BY THE REFERENCE NUMBER NRC STAFF DOCUMENT 126 Reliability of PWR LICENSING ISSUE Memorandum from Main Steam Safety (Resolved)
E.S. Beckjord, datei Valves March 10, 1988 127 Maintenance and Testing LOW Memorandum from of Manual Valves in E.S. Beckjord, dated Safety-Related Systems June 1, 1987 128 Electrical Power HIGH Memorandum from Reliability T.P. Speis, dated November 28, 1.986, and Supplement 6 to NUREG-0933 "A Prioritiza-tion of Generic Safety Issues," dated March 1987 130 Essential Service Water HIGH Memorandum from Puap Failures at Multi-H.R. Denton, dated plant Sites March 10, 1987 133 Update Policy Statement LICENSING ISSUE Memorandum from on Nuclear Power Plant H.R. Denton, dated Staff Working Hours February 25, 1987 134 Rule on Degree and HIGH Memorandum from Experience Requirement H.R. Denton, dated February 20, 1987 135 Steam Generator and MEDIUM Supplement 7 to NUREG-Steam Line Overfill 0933, "A Prioritiza-tion of Generic Safety Issues," dated March 1988 136 Storage and Use of LICENSING ISSUE Memorandum from Large Quantities of E.S. Beckjord, dated Cryogenic Corrbust-March 8,1988 ibles on Site
ATTACHMENT 1 LIST OF GENERIC ISSUES FOR WHICH THE ACR5 AGREE 5 WITH THE PRIORITY RANtINGS PROPOSED BY THE NRC STAFF 3
GENERIC ISSUE NO.
TITLE 8S Earthquakes and Emergency Planning 106 Piping and the Use of Highly Combustible Gases in Vital Areas 113 Dynamic Qualification Testing of Large Bore Hydraulic Snubbers 125.I.1 Availability of the Shift Technical Advisor 125.I.3 SPDS Availability 125.I.4 Plant Specific Simulator 125.I.6 Valve Torque Limit and Bypass Switch Settings 125.1.7.a Recover Failed Equipment 125.I.7.b Realistic Hands-on Training 125.I.8 Procedures and Staffing for Reporting to NRC Energency Response Center 125.II.1.a Two-Train AFW Vnavailability 125.II.1.b Review Existing AFW Systems for Single Failures 125.II.1.c NUREG-0737 Reliability Improvements 125.II.1.d AFW Steam and Fer-dwater Rupture Control System /ICS Interactions in B&W Plants 125.11.2 Assess the Adequacy of Existing Maintenance Require-ments and Their Impact on the Resulting Reliability of Safety-Related Systems 125.11.5 Thermal-Hydraulic Effects of Loss and Restoration of Feedwater on Primary System Components
Generic Issues - Attachment 1 j 125.11.6 Reexamine PRA-based Ectimates of the Likelihood of a Severe Core Damage Accident Based on Loss of All Feedwater 125.11.8 Reassess Criteria for Feed-and-Bleed Initiation 125.11.10 Hierarchy of Impromptu Operator Actions 125.II.12 Adequacy of Training Regarding PORV Operation 125.11.13 Operator Job Aids 126 Reliability of PWR Main Steam Safety Valves 128 Electrical Power Reliability 130 Essential Service Water Pump Failures at Multi-Plant Sites 133 Update Policy Statement on Nuclear Power Plant Staff Working Hours 136 Storage and Use of Large Quantities of Cryogenic Combustibles on Site F
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ATTACHMENT 2 GENERIC ISSUES FOR WHICH THE ACRS AGREES WITH THE PROPOSED PRIORITY RANKING BUT WITH COMMENT 5 Generic Issue No:
127
Title:
Maintenance and Testing of Manual Valves in Safety-Related Systems Priority Ranking Proposed By The NRC Staff:
The.L e jrees with the proposed priority ranking for v.
issue, but offers the coment given below.
Certain manual valves which may or may not be located in safety-related systems are identified in safety analyses or emergency procedures for manipu-lation during low-probability '
a tions such as transients or accidents inYolv Q Mlltiple Component or system failures. There sho s; w a rey irement for surveillance and testing of such manual valves.
This could be covered under a new generic issue or included as an extension of the severe accident program.
Generic Issue No:
135
Title:
Steam Generator and Steam Line Overfill Priority Ranking Proposed By The NRC Staff:
MEDIUM ACRS' Coments:
The ACRS agrees with the proposed priority ranking for this issue, but offers the coment given below.
With the sudden, complete, and unexpected steam generator tube rupture event that occurred at the North Anna Nuclear Plant on July 15, 1987, it would appear that another mechanism for initiating an overfill scenario has been discovered. This would indicate that the mechanisms for initiating steam generator and steam line overfill are not yet ccepletely understood. The Staff should consider such mechanisms under this Generic Issue, and should reccgnize that new operating experience could change current expectations of the frequency of steam generator and steam line overfill events.
ATTACHMENT 3 GENERIC ISSUE FO.' WHICH THE ACRS DISAGREES WITH THE PRIORITY RANKING PROPOSED BY THE NRC STAFF Generic Issue rio:
134
Title:
Rule on Degree and Experience Requirement Priority Ranking Proposed By The NRC Staff:
HIGH ACRS Recommendation:
DROP Reasons:
In its report of August 12, 1987 to the Commis-sion regarding degree requirements for senior operators, the ACRS commented:
AnumberofJobandTaskAnalyses(JTAs) have been performed by licensees as part of the conversion to performance based training; analysis of these JTAs has not shown that a college degree is necessary for Senior Reactor Operators (SP.0s) to perform the tasks of their jobs to ensure safety of plant operations. A Peer Advisory Panel appointed by the Commission came to the same conclusion in 1982 and recontended against a degree requirement for SR0s.
We have not been informed of any technical rationale for requiring a degree for SR0s at nuclear power plants; we conclude, therefore, that a degree requirement for all SR0s is primarily a policy issue.
Based on the above, the ACRS believes that this issue should be dropped from further consideration.
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