ML15261A107
| ML15261A107 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 06/01/1995 |
| From: | Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Hampton J DUKE POWER CO. |
| References | |
| GL-83-28, NUDOCS 9506190381 | |
| Download: ML15261A107 (25) | |
Text
June 1, 1995 Duke Power Company ATTN:
Mr. J. W. Hampton Vice President Oconee Site P. 0. Box 1439 Seneca, SC 29679 Gentlemen:
SUBJECT:
MEETING
SUMMARY
- OCONEE NUCLEAR STATION QA PROGRAM This refers to the management meeting conducted in the Region II office on May 1, 1995.
This meeting was a followup to the February 6, 1995, NRC/Duke management meeting, and focussed on issues discussed in the NRC response dated March 30, 1995, and the Oconee QA-1 licensing basis clarification submittal dated.April 12, 1995. A list of attendees and a copy of your presentation handout are enclosed.
Your presentation was beneficial, in that it provided the NRC staff with a background and a summary of your Oconee Safety-Related Designation (OSRD)
Clarification Project. Our understanding of the results of the meeting are as follows:
Duke stated that the Oconee QA-5 program is considered to be an addition to the current program described in the current licensing basis. As such, it will not be submitted as a commitment to the NRC, however the QA program will be revised to include a definition of the additional equipment category. QA-5 structures, systems and components (SSCs) with safety functions will receive additional quality treatment in the form of enhanced maintenance procedures and surveillance testing.
As stated in the April 12, 1995, submittal, Duke has deduced, from previous correspondence related to the design and licensing of Oconee, that the licensing basis for the definition of the scope of safety related equipment was a large break loss of coolant accident coincident with a loss of offsite power (LOCA/LOOP).
The April 12, 1995, submittal also contained a revised, Oconee response to Generic Letter 83-28, "Required Actions Based on Generic Implications of Salem ATWS Events."
NRR agreed to review the April 12, 1995, submittal, and respond by August 1, 1995, providing the NRC position on the description of the original licensing basis. NRR will also review the licensing basis as modified by the Duke responses to GL 83-28.
9506190381 950601 PDR ADOCK 05000269 P
DPC 2
Separate meeting arrangements will be made by NRR if further discussions are required to further the review of the Oconee licensing bases.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practise," a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
Should you have any questions concerning this letter, please contact me at 404-331 5680.
Sincerely, Original signed by Albert F. Gibson Albert F. Gibson, Director Division of Reactor Safety Docket Nos.
50-269, 50-270, 50-287 License Nos.
DPR-38, DPR-47, DPR-55 Attachments: as stated cc:
Mr. J. E. Burchfield Compliance Mr. Max Batavia, Chief Duke Power Company Bureau of Radiological Health P. 0. Box 1439 South Carolina Department of Health Seneca, SC 29679 and Environmental Control 2600 Bull Street Mr. A. V. Carr, Esq.
Columbia, SC 29201 Duke Power Company 422 South Church Street County Supervisor of Charlotte, NC 28242-0001 Oconee County Walhalla, SC 29621 Mr. Robert P. Gruber Executive Director Manager, LIS Public Staff - NCUC NUS Corporation P. 0. Box 29520 2650 McCormick Drive Raleigh, NC 27626-0520 Clearwater, FL 34619-1035 Mr. Robert B. Borsum Mr. G. A. Copp Babcock and Wilcox Company Licensing - ECO50 Nuclear Power Generation Division Duke Power Company 1700 Rockville Pike, Suite 525 P. 0. Box 1006 Rockville, MD 20852 Charlotte, NC 28201-1006 Mr. J. Michael McGarry, III, Esq.
Ms. Karen E. Long Winston and Strawn Assistant Attorney Genera]
1400 L Street, NW N. C. Department of Justice Washington, D. C. 20005 P. 0. Box 629 Raleigh, NC 27602 Office of Intergovernmental Relations 116 West Jones Street Raleigh, NC 27603
DPC 3
Distribution:
A. Gody, DISP/PIPB G. Tracy, OEDO L. Kokajko, OEDO R. Crlenjak, RII R. Carroll, RII Docket File PUBLIC L. A. Wiens, NRR R. Gramm, NRR/TQMB R. Latta, NRR/TQMB RII Receptionist NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, SC 29672 SEND TO PUBLIC DOCUMENT ROOM?
YES NO OFFICE RII:DRS RII:DRS R(I:DRS DRP,
l SIGNATUREt NAME KE CCASTO TP BLES EMERSCHOFF HBorkow DATE 5/ j/95 5/1\\'/95 5/
/95 5/ 1/95 5/0/95 5/h 95 OFFICIAL RECORD COPY bOMN NAME: %U3S\\CO.M5TG-
ATTACHMENT DPC List of Attendees for the May 1, 1995 meeting NRC Attendees S. Ebneter, Regional Administrator, Region II (RII)
J. Lieberman, Director Office of Enforcement E. Merschoff, Director, Division of Reactor Projects (DRP), RII A. Gibson, Director, Division of Reator Safety (DRS), RII H. Berkow, Director, Project Directorate 11-2 (PDII-2), Office of Nuclear Reactor Regulations (NRR)
B. Uryc, Director, Enforcement Staff, RII R. Crlenjak, Chief, Reactor Projects Branch 3, DRP, RII J. Blake, Chief, Materials and Processes Section, DRS, RH R. Gramm, Section Chief, Quality Assurance and Maintenance Branch (TQMB),
Division of Technical Support (DOT), NRR L. Kokajko, Office of the Executive Director for Operations (0EDO)
R. Latta, TQMB, DOT, NRR L. Wiens, Oconee Project Manager (PM), PDII-2, NRR W. LeFave, Plant Systems Branch (SPLB), Division of Systems Safety & Analysis (DSSA), NRR P. Harmon, Senior Resident Inspector (SRI) Oconee, DRP, RII P. Humphrey, RI Oconee, DRP, RII R. Carroll, Project Engineer, DRP, RII Duke Power Company Attendees J. Hampton, Vice President, Oconee Nuclear Station (ONS)
J. Davis, Engineering Manager, ONS W. Foster, Safety Assurance Manager, ONS B. Estaque, Commodities Manager J. Burchfield, Regulatory Compliance Manager, ONS C. Little, Electrical Engineering Manager, ONS H. Hammond, Senior Engineer, Duke R. Colaianni, Senior Engineer, License Renewal, Duke J. Warren, Senior Engineer, Duke D. Coyle, Mechanical Engineer, ONS D. Dalton, Electrical System Support, ONS M. Miller, Electrical Systems Engineer, ONS S. Nader, Mechanical Engineer, ONS
ATTACHMENT Second NRC/Duke Management Meeting on Oconee Safety Related Designation Clarification (OSRD) Issues Duke Power Company
Meeting Agenda
- Status of OSRD Project
- Discussion of March 30, 1995 NRC
Response
- Discussion of QA-5 and the Maintenance Rule
- Duke/NRC Approval Sequence
- Management Summary Duke Power Company
Status of OSRD Project
- In the February 6, 1995 meeting, Duke and NRC met to discuss safety-related equipment classification issues at Oconee.
- In this meeting, Duke proposed a process to resolve equipment classification issues at Oconee.
- This process is called the Oconee Safety-Related Designation Clarification (OSRD) Project.
Duke Power Company
Status of OSRD Project
- The OSRD Project will:
Clarify Oconee QA-1 licensing basis and obtain NRC approval.
Verify Oconee QA-1 SSCs are properly categorized.
Identify non QA-1 SSCs at Oconee that warrant an augmented quality standards program.
> Develop a program to maintain this quality standard.
Duke Power Company
ONS SAFETY-RELATED DESIGNATION PROJECT DEVELOPDEVELOP DEVELOP ACCIDENT SAFETY SSCs NO ACTION FUNCTIONS REQUIRED YES VERIFY LB YES CURRENTLY ORIGINAL SUBMITTAL EN CDESIGNATED AGREEMENT LB/LC LB 4/15/95 QA-1 NO NO REVIEW LICENSINGpp COMMITMENTS DEVELOP REVISE IMPLEMENT 0 QA-5 QAQA-5 APPROPRIATE PROGRAM CRITERIA LIST ON CRITERIA DOCUMENTS 4/15/95 EQUIPMENT NO Train Personnel DEVELOP NON-SAETY]
Revise Duke Topical QA-5 Revise Drawings PROGRAM Revise MPs/PTs/IPs Revise QA/QC Procedures 4th QTR 95 Revise System/Site Directives Revise Work Control Processes 2/3/95
ONS SAFETY-RELATED DESIGNATION PROJECT COMPLETED ACTIVITIES IDEVELOP CCIEVEOPDEVELOP DEVELOP ACCIDENT SAFETY SSCs NOACTION LISTNOATN LTFUNCTIONS REQUIRED YES VERIFY LBis YES CURRENTLY DUKE/NRC SSC IN 4
QA-1 LIST ORIGINAL SUBMITTAL AGREEMENT DESIGNATED AGREMENT LB/LC LB 4/15/95 QA-1 NO NO REVIEW LICENSING PIP COMMITMENTS MEET DEVELOP Z
IMPLEMENT QA5 QAQA-5A-5 PROGRAM CRTEI APPROPRIATE ON CRIERI CRITERIA LIS DOCUMENTS O
4/15/95 EQUIPMENT NO Train Personnel DEVELOP NON-SAFETY Revise Duke Topical QA-5
-Revise Drawings PROGRAM Revise MPs/PTs/lPs 4th QR 95Revise QA/QC Procedures 4th QTR 95 Revise System/Site Directives Revise Work Control Processes 4/26/95
ONS SAFETY-RELATED DESIGNATION PROJECT IN PROGRESS ACTIVITIES DEVELOPDEVELOP DEVELOP ACCIDENT SAFETY SSCsNOATN LIST NO ACTION L. IST
~
FUNCTIONS RQIE REQUIRED YES VERIFY LB is YES CURRENTLY ORIGINAL SUBMITTAL DGUEEMENC SSCIN QA-1 LIST DESIGNATED LB 4/15/95 GEMNL/CQ REVIEW LICENSINGISNON IPIP QA-5 P_
QA -5 QA-5 APORTE PROGRAM CRITERIAAPPROPRIATE ON CRITERIA DOCUMENTS 4/15/95 EQUIPMENT Train Personnel NON-SAFETY Revise Duke Topical Revise Drawings.
Revise MPs/PTs/IPs Revise QA/QC Procedures Revise System/Site Directives Revise Work Control Processes 4/26/95
Status of OSRD Project
- Duke committed to complete several items in the OSRD Project prior to this meeting:
> Make a submittal to clarify the Oconee QA-1 licensing basis.
Develop a list of Oconee accidents with QA-5 accidents identified.
>> Establish a QA-5 criterion to apply to non QA-1 SSCs that mitigate QA-5 accidents.
- These items have been completed.
Duke Power Company
Status of OSRD Project
- Oconee QA-1 licensing basis clarification submittal to NRC dated April 12, 1995.
- Submittal addressed the following:
> Oconee's QA-1 Licensing Basis History
>> Oconee's clarified QA-1 Licensing Basis
>> Proposal on addressing issues with Subpart 1 of Section 2.2.1 of Generic Letter 83-28
>> Oconee Accident List with QA-5 Accidents identified
>> QA-5 Criterion Duke Power Company
Status of OSRD Project
- Our submittal:
>> provides a clear dividing line between QA-1 SSCs and non QA-1 SSCs which prevent or mitigate the consequences of accidents.
> shows why the SSC scope of the QA-1 program at Oconee is unique.
>> clarifies that Oconee's licensing basis focused on SSCs essential to mitigation of LBLOCA/LOOP and other primary systems whose radioactive releases could impact the health and safety of the public.
Duke Power Company 10
Status of OSRD Project
- The following tasks are in progress:
-Achieve Duke/NRC agreement
- QA-5 program development
- Licensing commitments review Duke Power Company
Status of OSRD Project inUUU........
- The following tasks are planned:
- Development of accident mitigation safety functions and list of SSCs
- Revise QA-1 Checklist
- Develop QA-5 Checklist
- Classification of accident mitigation SSCs
- QA-5 program document revisions
- QA-5 program implementation Duke Power Company 12
Discussion of the March 30, 1995 NRC
Response
Letter
- Oconee Management would like to specifically address two items in the NRC's March 30, 1995 letter response to our proposed program. These items are:
> QA Topical Report incorporation of QA-5.
>> QA-5 Procurement.
Duke Power Company 13
Discussion of the March 30, 1995 NRC Response Letter
~
~
- Incorporation of QA-5 into Duke's QA Topical Report.
> The "definition" of QA-5 will be incorporated into the QA Topical Report.
> Will be similar to incorporation of QA-3 and QA-4 in the QA Topical Report
>> The QA-5 program requirements will be implemented through Duke directives and procedures.
Duke Power Company 14
Discussion of the March 30, 1995 NRC Response Letter
- QA-5 Procurement
>> QA-5 parts procurement will be conducted in the same structured manner as procurement of non-safety parts.
Duke Power Company 15
Discussion of the March 30, 1995 NRC
Response
Letter
- QA-5 Procurement (cont'd)
>> We believe our QA-5 program will ensure that these SSCs meet their intended design functions.
> Normal procurement practices combined with installation and post installation practices essentially the same as QA-1 will provide this assurance.
Duke Power Company 16
Discussion of the March 30, 1995 NRC Response Letter
- QA-5 Procurement (cont'd)
>> Procurement
> Installation
>> Post-Installation Duke Power Company 17
Discussion of QA-5 and the Maintenance Rule
- The MR screening criteria bounds QA-5.
- The MR also recognizes that non-safety equipment is used for accident mitigation.
- In the unlikely event that any additional systems are identified through the development of the QA-5 Accident charts, these systems will be included in the MR.
Duke Power Company 18
Duke/NRC Approval Sequence
- Original QA-1 Licensing Basis 0
> Duke submitted April 12, 1995.
>> NRC SER requested August 1995.
- Post-license QA-1 SSC Commitments
>> Duke followup submittal by September 1995.
>> NRC SER requested December 1995.
- QA Topical Report
> Duke amendment for QA-5 by August 1995.
> NRC Approval requested October 1995.
- Duke proceeds with QA-5 program implementation Duke Power Company 19
Management Summary
- Duke met commitments from Feb 6th Meeting
- Project initiatives are proceeding
- Project schedule has been developed
- NRC approval of licensing basis and support of QA-5 program are key to project success
- Additional issues needing agreement
> GL 83-28
> QA-5 Program documentation method
> QA-5 Parts procurement
- Duke is committed to completion of OSRD Project Duke Power Company 20
SARLY ARLY UIU KM995 1996 1997 START FINISH DUR DUR PCT JAN FEB MAR APR Y JUN JUL AUG SEP ocr NOV DBC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB MAP APR M
16JAN95A 13JAN97 409 352 15 M
OSRD PROJECT 13JAN97 0
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OSRD LOSE OUT REPORT' 16JAN95A 11NOV96 373 316 60 I
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~NC SS CLASSIFICATION PRSN INII 16JAN95A 6FEB95A 13 0
100 NR ES ATION 16JAN95A 3JUL95 95 40 so LICENSING CORRESPONDENCE REVIEW 16FEB9SA 20MAR95A 18 0
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,I JI 13MAR95A 13APR9SA 20 0
100 A-1 LICENSE BASES 3APR9sA 1MAY9SA 17 o
1oo NRC QA-1 LICENSE BASIS PRESENTATION 8APR96 13MAY96 21 21 0
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I NRC ACCIDENT SSC PRESENTATION 9SEP96 11NOV96 37 37 0
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1 NRC SSC CLASSIFICATION INFORMATION SUBMITTAL 3JUL95 3AUG95 19 19 0
LICENSE CORRESPONDENCE REVIEW SUBMITTALC 19JAN95A 2SEP96 330 276 18 SSC CLASSIFICATION ACTIVITIES 19JAN9SA 3JUL95 92 40 70 Q
C IION 20CT95 1APR96 100 100 5
1 1ACCIDENT MITIGATION AND SSC LIST 9FEB9SA 4APR95A 26 0
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QA-5 CRITERIA FOR NRC PRESENTATION I
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CLASSIFICATION OF ACCIDENT MITIGATION SSC"S 5JUN95 5SEPSS 53 53 0
AC IDENT MITIGATION CHART PILOT 20FEB95A 31DEC96 382 345 5
QA S PROGRAM ACTIVITIE 20FEB95A 30JUN95 74 39 25 QA-5 PROGRAM DEVELOPMENT.
12JUN95 30JUN95 13 13 5
QA-5 PRO RAM RECOMMENDATION 3JUL95 31JUL95 16 16 0
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