ML13336A103
| ML13336A103 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/27/1988 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8808170343 | |
| Download: ML13336A103 (33) | |
Text
July 27, 1988 Docket No. 50-206 FACILITY:
SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 LICENSEE:
SOUTHERN CALIFORNIA EDISON COMPANY (SCE)
SUBJECT:
SUMMARY
OF MEETING HELD ON JUNE 28, 1988 AT THE SAN ONOFRE SITE TO DISCUSS THE LICENSING PROCESS AND 10 CFR 50.59 REVIEWS.
On June 28, 1988, the NRC staff met with representatives of SCE at the San Onofre site to discuss the licensing process and 10 CFR 50.59 reviews.
Persons attending the meeting are identified in Enclosure 1. The meeting agenda and related handouts are contained in Enclosure 2. The meeting was held pursuant to notice issued on June 21, 1988.
The meeting covered engineering support and outage planning, the license amendment process followed by SCE, Edison's 50.59 procedures, the role of the various review committees, the status of FSAR update for Unit 1, and reporting requirements, with particular emphasis in each area on the roles of home office personnel and site personnel and how each is kept abreast of the activities of the other.
The meeting was similar to others held for each of the facilities in Project Directorate V, but was prompted by recent licensing difficulties regarding spent fuel transshipment and disagreements concerning interpretation of 10 CFR 50.59. NRC is presently working on a guidance document on this subject which should be useful in applying this regulation.
The meeting was very helpful to the NRC staff in gaining a better familiarity of Edison operations at San Onofre.
original signed by 808170343 880727 T
Charles M. Trammell, Senior Project Manager PDR ADOCK 5000206 1
Project Directorate V PNU _
Division of Reactor Projects - III, IV, V and Special Projects
Enclosures:
- 1. Attendees
- 2. Viewgraphs DISTRIBUTION Docket File OGC-WF DKirsch PDR EJordan Plant Service List (See next page)
LPDR BGrimes Licensee PDV Reading NRC Participants RHuey GKnighton ACRS (10)
Project Manager Johnson PDV DSP/D:PDV mmell:dr GWKnighton 8
CI8 7
R7/R8 o
OFFICIAL RECORD COPY 1
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 2056 July 27, 1988 Docket No. 50-206 FACILITY:
SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 LICENSEE:
SOUTHERN CALIFORNIA EDISON COMPANY (SCE)
SUBJECT:
SUMMARY
OF MEETING HELD ON JUNE 28, 1988 AT THE SAN ONOFRE SITE TO DISCUSS THE LICENSING PROCESS AND 10 CFR 50.59 REVIEWS.
On June 28, 1988, the NRC staff met with representatives of SCE at the San Onofre site to discuss the licensing process and 10 CFR 50.59 reviews.
Persons attending the meeting are identified in Enclosure 1.
The meeting agenda and related handouts are contained in Enclosure 2. The meeting was held pursuant to notice issued on June 21, 1988.
The meeting covered engineering support and outage planning, the license amendment process followed by SCE, Edison's 50.59 procedures, the role of the various review committees, the status of FSAR update for Unit 1, and reporting requirements, with particular emphasis in each area on the roles of home office personnel and site personnel and how each is kept abreast of the activities of the other.
The meeting was similar to others held for each of the facilities in Project Directorate V, but was prompted by recent licensing difficulties regarding spent fuel transshipment and disagreements concerning interpretation of 10 CFR 50.59. NRC is presently working on a guidance document on this subject which should be useful in applying this regulation.
The meeting was very helpful to the NRC staff in gaining a better familiarity of Edison operations at San Onofre.
Charles M. Trammell, Senior Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Enclosures:
- 1. Attendees
- 2. Viewgraphs cc:
See next page
Mr. Kenneth P. Baskin San Onofre Nuclear Generating 5outhern California Edison Company Station, Unit No. 1 cc Charles R. Kocher, Assistant Mr. Jack McGurk, Acting Chief General Counsel Jaesneletosquir Radiological Health Branch JamesState Department of Health Southern California Edison Company Services Post Office Box 800 714 P Street, Office Bldg. 8 Rosemead, California 91770 Sacramento, California 95814 David R. Pigott Mr. Hans Kaspar, Executive Director Orrick, Herrington & Sutcliffe Marine Review Committee, Inc.
600 Montgomery Street 531 Encinitas Boulevard, Suite 105 San Francisco, California 94111 Encinitas, California 92024 Mr. Robert G. Lacy Mr. Dennis M. Smith, Chief Manager, Nuclear San Diego Gas & Electric Company Radiological Programs Division San iegoGas Elctri ComanyGovernor's Office of Emergency Svcs.
P. 0. Box 1831 State of California San Diego, California 92112 2800 Meadowview Road Sacramento, California 95832 Resident Inspector/San Onofre NPS U.S. NRC P. 0. Box 4329 San Clemente,-California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego 1600 Pacific Highway Room 335 San Diego, California 92101 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1516 - 9th Street Sacramento, California 95814 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
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JUNE 28, 1988 MEETING AGENDA I.
INTRODUCTION M. 0. MEDFORD II.
ENGINEERING SUPPORT AND OUTAGE PLANNING J. K. YANN III.
LICENSE AMENDMENT PROCESS D. L. Cox IV.
50.59 PROCESS D. F. PILMER Dav V.
REVIEW COMMITTEES J. M. CURRAN Jr VI.
SONGS 1 FSAR UPDATE J. L. RAINSBERRY VII.
REPORTING REQUIREMENTS H. E. MORGAN
Corporate Organization
SOUTHERN CALIFORNIA EDISON EXECUTIVE ORGANIZATION HOWARD P. ALLEN CHAIRMAN OF THE BOARD, PRESIDENT. AND CHIEF EXECU1TVE OPPICER M. R.
PEEVEY D. J. FOGARTY J. E. BRYSON EXECUTIVE EXECUTIVE VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT a CHIEF FINANCIAL OMCER P. L.
MARM IL T. PAPAY SENIOR
%AE:I::DEA VICE PRESIDO T CORPORATE AND VC RSDN ADMINISTRATIVE POWER SUPPLY K. P. AMN N. B. RAY ft. DITCH
- f.
- v.
s5Mw M. L. NoLm J. R. BURY
. M.
%1 e"Mmw VIMK FRCUNf
%%Z PRSMD~
MIE PDW4T)E V=
MENDIT WKC PREOME4 MIE PM93MO0T eMt A
MATEIMA COWMO CUNSEL CustDMR ommm~m mcMAN~MENT 11111111"AIsanvior"C
SAN ONOFRE NUCLEAR GENERATION SITE CHARLES B. McCARTHY, JR.
VICE PRESIDENT AND SITE MANAGER H. E. MORGAN STATION MANAGER STATION DIVISIONS SUPPORT DIVISIONS D. R. HENICKE D. E. SHULL R. w. KRIEOUE J. T. REILLY P. J. KNAPP
- 8.
KATZ M. P. SHORT K. A. SAG
. p.
TMAINTENANCE OPERATIONS TECHNICAL PHEIH OM NUCLEAR MATL & ADMIN UDorr AM MANAGER MANAGER TRAINING SERVICES o
o M~iAOERMMANAGER MANAGER MANAGER MANAoERo-
NUCLEAR ENGINEERING SAFETY AND LICENSING DEPARTMENT KENNETH P. BASKIN VICE PRESIDENT NUCLEAR ENGINEERING.
SAFETY & LICENSING M. 0. MEDFORD J. M. CURRAN R. M. ROSENBLUM MANOMR OF MANAGER OF MANAGER OF AND UC0NN NUCLEAR SAFETY QUAUTY ASSURANCE E. N. CRAMER M. MoCREERY ENGINEER FOR NUCLEARMANAGER NUCLEAR NES&L SERVICES COMMUNICATIONS NSLSRIE
ENGINEERING AND CONSTRUCTION DEPARTMENT ROBERT DIETCH VICE PRESIDENT ENGINEERING AND CONSTRUCTION K. 0. GROTHUES S. V. TASHJIAN MANAGER OF MANAGER OF MANAGER OF COST ENGINEING ENGINEERING CONSTRUCTION PROJECTS AND SE ICES D. A. FELLOWS J. J. WAMBOLD NUCLEAR NUCLEAR GENERATION GENERATION ENGINEERING PROJECTS
JURISDICTIONS NUCLEAR GENERATION SITE OWNERSHIP OF PHYSICAL PLANT OPERATIONS MAINTENANCE SURVEILLANCES ROOT CAUSE ANALYSES REGION V INTERFACE NUCLEAR ENGINEERING, SAFETY, AND LICENSING OWNERSHIP OF DESIGN BASIS AND LICENSING BASIS SAFETY ANALYSES REGULATORY INTERFACE SAFETY REVIEWS INDUSTRY PROBLEM EVALUATIONS ENGINEERING AND CONSTRUCTION OWNERSHIP OF PLANT DESIGN NON-SAFETY RELATED DESIGN CRITERIA CONCEPTUAL ENGINEERING DESIGN PROCESS IMPLEMENTATION (INSTALLATION AND TESTING)
SAN ONOFRE NUCLEAR GENERATION SITE PLANT MODIFICATION REVIEW PROCESS Pre-Approval Bulletins PR*
NES&L Eq. Failure
- Station
- Project New htems Conceptual Evaluation Pkg.
- Descriptive Scope Summary E&C NESL
- Reason for Request 0 t Licensing
- NES&L Approval
- Station
- Mai nability Estimating
- Project User Defines Issu
- Discussion of Alternatives Coceptual Cost/
PMRC Need for mr Estimate Benefit Approval/
WR IniiatEon Number
- Conceptual Scope of Work Analysis Disapproval Mgr./Tech.
- SketchlDrawlngs Priority
- Equipment Affected
- Adds, Removes, Rearrange
- Approximate Time Frame
- SCE/Contract Benefits to Operations
SAN ONOFRE NUCLEAR GENERATION SITE PLANT MODIFICATION REVIEW PROCESS Configuration 100 Control 50%
Forms Design 183/184 Rve EAC 2t 715 EAC 24-10.17 E&C 24-10-15 Perform/
sope Of 10% Design Perform Prepare Perform Complete Work Review Analysis Interim Design Safety
[(1-b J Encepul Design inputs Meeting aW Design Review Notices (PFC)
E&C Long Lead Material Procurement Schedule and Monitor Work Sope
SAN ONOFRE NUCLEAR GENERATION SITE PLANT MODIFICATION REVIEW PROCESS Post-Approval Configuration Control Forms 183/184 E&C 24-10-16 1
8 E&C 24-10-15 Station Procedures E&C 24-R-7 Assemble Issue Inter-Comment issue Station Install Turnover DCN Design Carge Rev A orgizatonal Incorporation Rev 0 Review/
Modification and Incorporation Package/
DCP/PFC Review DCP/PFC Approval Acceptance Document Proposed Fielda Aclosurnc Facillty Change Walkdown Short Material Procurement Schedule and Monitor Work Scope IA
LICENSE AMENDMENT PROCESS o
Identification of change.
o Preparation of change.
o Internal review and approval.
o External review and approval.
o Status of Amendment Applications.
LICENSE AMENDMENT PROCESS IDENTIFICATION OF TECHNICAL SPECIFICATION CHANGE o
Changes to the SONGS Technical Specifications are identified by:
Licensing Station Engineering and Construction (Design Change)
Vendors (Analyses) o When identified to Licensing, technical justification may have been completed.
LICENSE AMENDMENT PROCESS PREPARATION OF TECHNICAL SPECIFICATION CHANGE o
Licensing takes lead.
o Required justification identified and analysis requested to be performed if applicable.
o Licensing prepares proposed change.
Description Safety Analysis Significant Hazards Considerations Determination Environmental Assessment
LICENSE AMENDMENT PROCESS SCE INTERNAL REVIEW o
SONGS Technical Specifications require Station Manager approval and NSG review.
o Station review includes, but is not limited to, the Station Manager, Operations, Maintenance, Station Technical, STAs.
o Review is an iterative process; generally a new proposed change will be prepared if significant revisions are involved.
o The approval process requires approximately three to five weeks.
COT
LICENSE AMENDMENT PROCESS EXTERNAL APPROVALS o
In parallel with the Technical Specification Change review process, a formal Amendment Application is assembled and transmitted to SCE's partners. SCE's partners include:
San Diego Gas & Electric (SONGS 1, 2 and 3)
The City of Anaheim (SONGS 2 and 3)
The City of Riverside (SONGS 2 and 3) o The external review and approval process requires two to three weeks.
o When review and approval of a proposed change is completed by SCE and partners, the change is submitted for NRC review.
LICENSE AMENDMENT PROCESS STATUS OF SUBMITTED AMENDMENT APPLICATIONS o
Unit I
- Currently 16 changes at NRR.
0 Units 2 and 3
- Currently 27 changes at NRR.
No. of Proposed Changes 0
<a
-o O
C, 0*
- 0)
L m
0 o
8 Total at NRC: 27 6
4)4 0
0 L.
0
- a.
te. 0 6
2 0
1984 1985 1986 1987 1988 Submittal Date
50.59 EVALUATIONS o
Evaluations are conducted for the following:
A.
Facility Changes
- 8.
Station Procedures and Programs o
50.59 Reviews are covered by detailed procedures o
Checklists are given with instructions o
Facility Changes are covered by E&C 24-10-15.
A.
Formal training is given to engineers who utilize this procedure.
B.
Records of training received are maintained for each individual.
FACILITY CHANGES o
Applicability A.
50.59 reviews are conducted for all physical changes within the protected area plus selected facilities outside this boundary.
o Safety Evaluations A.
Analysis of the safety significance is required which addresses the following:
- 1.
Probability and consequences of accidents.
- 2.
Possibility of accidents of a different kind.
- 3.
The margin of safety as defined in the basis for any technical specification.
B.
Effects of any kind are analyzed.
C.
Clear and detailed evaluations are required.
o Approvals A.
Safety evaluations are performed by qualified individuals.
B.
Cross-disciplinary reviews are performed prior to approval.
C.
Approvals are made prior to implementation by the Station Manager or by the Manager, Technical.
D.
Independent reviews are conducted by the Nuclear Safety Group.
SOUTHERN CALIFORNIA EDISON OVERSIGHT ORGANIZATIONS VICE PRESIDENTPRESIDENT NUCLEAR ENGINERIN, SAFETY NUCLEAR GENERATION SITE MANAGER OF MANAGER OF CEALY NU R
PLANT MANAGER QUALITY INDEPENDENT NUCLEAR ONSITE ASSURANCE/
SAFETY SAFETY REVIEW QUALITY ENGINEERING GROUP COMMITTEE CONTROL GROUP
SOUTHERN CALIFORNIA EDISON NUCLEAR CONTROL BOARDS THE NCB IS THE HIGHEST CORPORATE ORGANIZATION WHICH MEETS ON A REGULAR BASIS TO DISCUSS NUCLEAR SAFETY ISSUES.
NCB MEMBERSHIP CONSISTS OF:
Vice President of NES&L Vice President and Site Manager Vice President E&C Vice President SDG&E Manager of Engineering and Licensing Manager of Nuclear Engineering Manager of Quality Assurance Manager of Operations and Maintenance Support PROVIDES A SYNERGISTIC FORUM FOR VICE PRESIDENTS AND MANAGERS TO DISCUSS NUCLEAR SAFETY AND ENVIRONMENTAL ISSUES
SOUTHERN CALIFORNIA EDISON NUCLEAR SAFETY GROUP DESCRIBED IN THE SONGS 1, 2 & 3 TECHNICAL SPECIFICATIONS THE NSG PROVIDES INDEPENDENT TECHNICAL REVIEW OF:
Plant Equipment Changes Procedure Revisions Technical Specification and License Changes Violations of Requirements Significant Operating Abnormalities and Unanticipated Deficiencies in Design or Operations OSRC Activities TECHNICAL SPECIFICATION AUDITS ARE CONDUCTED BY QUALITY ASSURANCE PROPOSED TECHNICAL SPECIFICATION CHANGE Eliminate Routine Reviews Focus on Significant Safety Issues Anticipate Problems THE NSG IS A STAFF ORGANIZATION WITH A SUPERVISOR AND SIX (6) ENGINEERS.
ENGINEERS TYPICALLY HAVE 10 -
20 YEARS OF EXPERIENCE.
SOUTHERN CALIFORNIA EDISON ONSITE REVIEW COMMITTEES THE OSRC IS DESCRIBED IN THE SONGS 1, 2 & 3 TECHNICAL SPECIFICATIONS.
THE OSRC IS RESPONSIBLE FOR:
Investigating Technical Specification Violations Review of Operations to Detect Potential Nuclear Safety Hazards Review of Reportable Events Review of Prolonged Operation with Reactor Channels Out of Service THE OSRC MINUTES ARE REVIEWED BY THE NSG.
APPROVAL OF PROCEDURE REVISIONS, DESIGN CHANGES, AND LICENSE CHANGES IS CONDUCTED OUTSIDE THE OSRC MEETINGS.
SOUTHERN CALIFORNIA EDISON INDEPENDENT SAFETY ENGINEERING GROUP ISEG IS DESCRIBED IN THE TECHNICAL SPECIFICATIONS FOR SONGS 2 & 3.
ISEG IS RESPONSIBLE FOR IMPLEMENTING THE OPERATING EXPERIENCE FEEDBACK PROGRAM.
ISEG IS ALSO RESPONSIBLE FOR CONDUCTING SURVEILLANCE OF PLANT ACTIVITIES.
Unit 1 Safety Injection System Hydraulic Valves -
1988 Unit 1 Auxiliary Feedwater Pump Evaluation -
1987 Unit 2 HV-9378 Evaluation -
1987 Fuel Fragment Compensatory Action Program -
1987 ISEG IS A STAFF ORGANIZATION CONSISTING OF A SUPERVISOR AND SIX (6)
ENGINEERS TYPICAL EXPERIENCE LEVEL IS 20 YEARS.
SONGS 1 FSAR UPDATE METHODS INTERFACES STATUS
METHODS DOCUMENT REVIEW SOURCE FILE COMPUTER DATA BASE TEXT PREPARATION FORMAL REVIEW APPROVAL 00(oc J
INTERFACES DRAFT PREPARATION DATA SEARCH TECHNICAL INPUT FORMAL REVIEW QA PROCEDURE REVIEW & COMMENT RESOLUTION APPROVAL
STATUS SOURCE FILE -
95%
DRAFT PREPARATION - 60%
FORMAL REVIEW -
10%
DECEMBER 30 SUBMITTAL