ML20012F506
| ML20012F506 | |
| Person / Time | |
|---|---|
| Issue date: | 03/28/1990 |
| From: | Rothberg O NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Minners W NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20012F507 | List: |
| References | |
| NUDOCS 9004160039 | |
| Download: ML20012F506 (9) | |
Text
9 MAR 2 81990 s
MEMORANDUM FOR: Warren Minners, Director I
Division of Safety issue Resolution l
Office of Nuclear Regulatory Research i
FROM:
Owen Rothberg Engineering issues Branch Division of Safety Issue Resolution Office of Nuclear Regulatory Research THROUGH:
Frank Cherny, Section Leader Engineering issues Branch Division of Safety issue Resolution Office of Nuclear Regulatory Research l
l Robert Baer, Chief l
Engineering issues Branch Division of Safety Issue Resolution Office of Nuclear Regulatory Research Karl Kniel, Chief Reactor & Plant Safety issues Branch Division of Safety issue Resolution i
Office of Nuclear Regulatory Research
SUBJECT:
MEETING WITH NUMARC ON MARCH 14,1990 TO DISCUSS FORMAT AND CONTENT OF LICENSE RENEWAL APPLICATIONS NUMARC and NRC/RES both presented their views on the format and content of license renewal applications. A list of meeting attendees is attached along with hand outs from the meeting.
The major difference between the NUMARC and NRC proposals concerns the method of eliminating structures, systems and components (SSCs) important to l
license renewal from additional surveillance or study during the license renewal I
period. NUMARC's viewpoint is that SSCs that are subject to an " established effective program" to assure their continued satisfactory performance should not be.
subject to further study or surveillance. NRC/RES indicated that the preferred l
approach would be to identify age related degradation mechanisms for each SSC i
l-important to license renewal, and then determine if the established programs are, in i
fact, effective to address the identified aging mechanisms. The particular SSC would be eliminated from further study or surveillance after an analysis of the aging mechanisms and a comparison with the established program to verify that the program is truly effective.
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MAR 2 8 1990' The various aspects of each viewpoint were discussed at length. No final agreement was reached. NRC will outlin6 its proposed approach in a Draft Regulatory Guide (For Comment) by late 1990. NUMARC Intends to prepare a technical report on format and content of license renewal applications (See letter from E. Griffing, NUMARC to W. Travers, NRC dated 1/19/90, copy attached.)
although no specific format or dates for the ocyment were discussed at this meeting.
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Owen Rothberg Engineering Issues Branch Division of Safety issue Resolution Office of Nuclear Regulatory Research Attachments: As stated
Contact:
O. Rothberg x23924, NLS302 Distribution:
IPOR3 RES Chron E. Griffin G. Scott RES Circ T. Herowx L.Shao ElBr/f J. Grant G. Mizuno J. Vora W. Minners D. Cleary K. Kniel L. Marsh G. Sege l
R. Bosnak F. Akstulewicz M. Virgilio l
M. Vagins B. Sadanskas T. King J. Gilchrist P. Sears R. Baer W. Hinkle J.Thoma F. Cherny D. Edwards K. Cozeps O. Rothberg
[NUMAR1. DOC]
- SEE PREVIOUS CONCURRENCE ElB:DSIR ElB:DSIR ElB:DSIR RPStB:DSIR ORothberg/mb FCherny RBaer KKniel
- 03/20/90
- 3/20/90
- 3/20/90
- 3/21/90 OFFICIAL RECORD COPY
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2 The various aspects of each viewpoint were discussed at IJen th. No final agreement was reach C will outline its proppsed1pproach in a Draft Regulatory Guide (For Commen to errt989. NUMARC intends to prepare a technloal report on format and conter4'O rgrenewal applications (See letter from E. Griffing, NUMARC to)WTravers, NRC datGd4 9/90, copy attached.)
l although no specific f or dates for the document wer iscussed at this meeting.
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s Owen Rothberg Engineering Issues Branch Division of Safety issue Resolution Office of Nuclear Regulatory Research i
Attachments: As stated
Contact:
O. Rothberg x23924, NLS302 Distribution RES Chron E. Griffin G. Scott RES Cire T. Herowx L.Shao ElBr/f J. Grant G. Mizuno J. Vora W. Minners D. Cleary K. Kniel L. Marsh G. Sege i
R. Bosnak F. Akstulewicz M. Virgilio M. Vagins B. Sadanskas T. King l
J. Gilchrist P. Sears R. Baer W. Hinkle J.Thoma F. Cherny l
D. Edwards K. Cozevs O. Rothberg I
i
{NUMAR1. DOC]
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f' DRAFT REGULATORY GUIDE f
TECHNICAL INFORMATION FORMAT AND CONTENTS FOR NUCLEAR POWER PLANT OPERATING LICENSE RENEWAL APPLICATIONS CONTENTS' l
INTRODUCTION...................................................... Pace A.
l~
- a. DISCUSSION.........................................................
4 i
1.
SELECTION Of SSC IMPORTANT TO LICENSE RENEWAL..................
A I
2.
ELEMENTS Of AN EFFECTIVE PROGRAM TO ADDRESS AGING DEGRADATION..
6 2A.
UNDERSTANDING AGING DEGRADAT10N...........................
6
- a. Materials.............................................
6 I
b.
Design and Environmental Condition 7
Stressors.........................s...................
c.
7
( 1 ) Mechan i cal St re s sors.............................
(2) Electrical Stressors...........................
(3) Thermal Stressors..............................
d.
Aging Degradation Mechanisms.........................
10
( 1 ) C o r ro s i o n......................................... 1 0 0xidation......................................
Pitting........................................
l Intergranular Attack...........................
Stress Corrosion Cracking......................
Microbially-Induced Corr (2) Erosion....................osion..................
Erosion-Corrosion...................,...,.
12 l
Erosion-Cavitation...................
l (3) Embrittlement...........................
Neutron irradiation...........................
13 l
l Thermal Embrittlement...........
Hydrogen Damage.................
(4) Mechanical Degradat ion Mechani sms................
14 Fatigue........................................
W0Br...................................
Shrinkage and Creep............................
(5) Degradation Due to Operational Environmen 1
Deg rad a t i on Si t es............................ t.......
17 i
e.
l f.
Root Cause Determination.............................
17 l
riANAGI NG AGING DEGRADATION. r..........'..................
18 2B, Monitoring Aging Degradation.........................
19 a.
20 (1) Non Destructive Examination.......................
(2) Condition Monitoring....................
l (3) Surveillance, Testing, and Inspection Programs....
i (4) Residual Life Assessment..........
L b.
Mitigating Aging......................
23 l
(1) Preventive Maintenance.....................
(2) Corrective Meintenance.....................
(3) Risk-Based and Reliability Centered Maintenan l
Recordkeeping and Trending.....................ce c.
25 3.
TECHN] CAL INFORMATION REQUIREMENTS FOR L] CENSE RENEWAL....
27
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- D_RA_F_N CONTFNTS (CONT'D) l C.
REGULATORY POSIT10N...............................................
28 1.
SSC REQUIRING CONSIDERATION OF AGING IN SUPPORT OF LICENSE RENEWAL.....................................................
29 2.
ESTABLISHING EFFECTIVE PROGRAMS FOR ADDRESSING AGE RELATED DEGRADAT10N.................................................
32 2A.
SUMMARY
OF ACCEPTABLE PRACTICES FOR UNDERSTAND AG I NG DE GRADAT 10N................................ I NG
..s.........
33 28.
SUMMARY
OF ACCEPTABLE PRACTICES FOR MANAG DE GRADAT 10N................................. I N G AG I N
................. 35 3.
INFORMATION REQUIREMENTS FOR LICENSE RENEWAL..................
37 Technical Content of License Renewal Application..........
37 a.
b.
Information To Be Retained By The Licensee................
40 D.
IMPLEMENTATION.....................................................
44 BIBLIOGRAPHY..........................................................
45 FIGURES 1.
Process for Selecting Components important to License Renewal and Establishing an Effective Pro Aging Degradation............ gram for Understanding and Managing 46 2.
Interactive Licensee--NRC Staff Process f Application Review.......................or License Renewal 47 TABLES 1.
Generic Functional Criteria for SSC Important to License Renewal... 30 i
11.
Technical Information Requirements for License Renewal............. 41 APPEN0lX A.
SYSTEMS, STRUCTURES, AND COMPONENTS IMPORTANT TO LICENSE RENEWAL' IN 1. PWRs AND 11. BWRs............................................
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.I LICENSE RENEWAL APPLICATION FORMAT & CONTENT o
FIRST LICENSE MODEL:
REa GUIDE 1.70 o
RENEWAL MODEL:
REs Gu1DE " TECHNICAL INFORMATION" o
ASSETS:
UFSAR NUMARC OUTLINE METHODOLOGY INDUSTRY REPORTS i
i 3/14/90 i
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APPLICATION FORMAT AND CONTENT GUIDELINE OUTLINE I
O INTRODUCTION i
0 DEFINITIONS O
CHARACTERIZATION AND
SUMMARY
OF FINDINGS i
O SAFETY ANALYSIS O
PLANT SPECIFIC EXEMPTIONS l
P 0
ENVIRONMENTAL ANALYSIS O
SAFETY ANALYSIS 0
DESCRIPTION OF PLANT-SPECIFIC APPLICATION OF "THE METHODOLOGY T0 e
EVALUATE PLANT EQUIPMENT FOR LICENSE RENEWAL" O
SELECTION OF SYSTEMS / STRUCTURES FOR FURTHER REVIEW r
0 COMPONENT LEVEL EVALUATION BY SYSTEM / STRUCTURE 9
0
SUMMARY
OF SAFETY ANALYSIS FINDINGS l
l d
MARCH 14, 1990 g.
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1 APPLICATION FORMAT AND CONTENT GUIDELINE OUTLINE 1
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0 PLANT SPECIFIC EXEMPTIONS j
1 0
EXANINATION OF EXEMPTIONS 1
0
SUMMARY
OF EXEMPTION FINDINGS J
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0 ENVIRONMENTAL ANALYSIS i
0 REVIEW 0F ENVIRONMENTAL INTERFACES 0
EVALUATION OF ENVIRONMENTAL EFFECTS t
O
SUMMARY
OF ENVIRONMENTAL FINDINGS i
i O
IMPLEMENTATION PLAN P
l 0
SUMMARY
OF COMMITHENTS i
0 DESCRIPTION OF ADMINISTRATIVE CONTROLS O
TASKS AND SCHEDULE O
REFERENCES 7
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I l
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i I
MARCH 14, 1990
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