ML13333B868
| ML13333B868 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/18/1983 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR LSO5-83-03-037, LSO5-83-3-37, NUDOCS 8303230241 | |
| Download: ML13333B868 (45) | |
Text
March 18, 1983 Docket No. 50-206 LS05-83-03-037 LICENSEE:
SOUTHERN CALIFORNIA EDISON COMPANY FACILITY:
San Onofre Nuclear Generating Station, Unit No. 1
SUBJECT:
SUMMARY
OF FEBRUARY 17, 1983 MEETING (SEP TOPIC 111-6, SEISMIC DESIGN CONSIDERATIONS)
On February 17, 1983, members of the NRC staff met with representatives of Southern California Edison Company (SCE). The purpose of the meeting was to discuss SCE's proposed resolution of outstanding issues regarding Systematic Evaluation Program Topic III-6, Seismic Design Considerations.
Enclosure I is a list of attendees.
The licensee discussed (1) the method of combining seismic anchor movement and inertia responses of piping, (2) methods of calculating seismic anchor movement stresses, and (3) the effect of the sphere enclosure building on the reactor building analysis. Enclosure 2 is.a copy of the viewgraphs used by the licensee is discussing items 1, 2, and 3 above.
At the conclusion of the meeting, the NRC staff stated that the following are acceptable: (1) the method for the combination of seismic anchor movement and seismic inertia responses of piping, and (2) the acceptanck criteria for the SSE anchor motion including the augmented class 2/3 evaluation method based on 100 maximum stress cycles.
With regard to the use of a single time history for the reactor coolant loop, the NRC staff indicated that additional review would be necessary.
The licensee did not include the sphere enclosure building in the seismic analysis of the reactor coolant loop, The licen'see stated that the presence of the sphere enclosure building will decrease the seismic response of the NSSS support locations. The staff needs to review the modeling of the sphere enctosure building and the reactor building and containment sphere. In addition, the staff needs to review the sensitivity studies of the steam generators to determine if the NSSS is insensitive to phasing.
The licensee stated that they will send a letter shortly after the meeting stating that they are meeting the NRC criteria with a few exceptions; the exceptions will be as addressed at the meeting. The licensee will sent in the project criteria document at a later date for NRC's review and approval.
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SURNAME DATE NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
- 2March 18, 1983 In the afternoon, the licensee discussed a proposed plan for early return to power for San Onofre Unit 1. This facility has been shutdown since February 27, 1982 for seismic upgrading and other work including steam generator inspection. Enclosure 3 is a set of handouts provided by the licensee. The licensee's plan would assure that the structures and systems whose failure could cause an accident or which are required to yet to a safe cold shutdown will be available following a 0.67g earthquake. Structures and systems not required to get to a safe cold shutdown will be deferred. The licensee indicated that they are currently planning on restart in September 1983. The licensee's long range plan is to operate San Onofre Unit No. 1 for the eighteen month cycle and then shutdown for three months to perform modifications/additions required by the NRC and also to make those plant improvements desired by the licensee.
This long-range schedule is dictated by the cost of the modifications/
additions.
A meeting with top NRR management is to be arranged followed by a formal submittal of the restart plan.
Original signed by Walter A. Paulson, Project Manager Operating Reactors Branch 75 Division of Licensing
Enclosures:
As stated cc w/enclosures:
See next page DL/
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DATEb NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
3 -
March 18, 1983 cc Charles R. Kocher, Assistant General Counsel James Beoletto, Esquire Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David R. Pigott Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111 Harry B. Stoehr San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o 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 San Diego, California 92101 California Department of Health ATTN:
Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814 U. S. Environmental Protection Agency Region IX Office ATTN:
Regional Radiation Representative 215 Freemont Street San Francisco, California 94111 Robert H. Engelken, Regional Administrator Nuclear Regulatory Commission, Region V 1450 Maria Lane Walnut Creek, California 94596
ENCLOSURE 1 ATTENDANCE LIST February 17, 1983 Meeting San Onofre Unit 1 NAME AFFILIATION W. Paulson NRC R. W. Krieger SCE J. Rainsberry SCE E. McKenna NRC T. M. Cheng NRC R. W. Macek EG&G Idaho Drew Persinko NRC D. Crutchfield NRC William Lapay W
Paul Koss Bechtel Selcuk Atalik Bechtel G. W. Gartland SCE Art Cimento EDS Nuclear Rick Ellis Bechtel Flo Mangan W
D. K. Nelson SCE Ken Baskin SCE H. Peters SDG&E W. Russell NRC
ENCLOSURE 3 PLAN FOR EARLY RETURN TO POWER SAN ONOFRE UNIT 1 o
General Provisions o
Specific Aspects o
Program for NRC Approval
SEISMIC REEVALUATION PROGRAM TOTAL SCOPE The scope of items reevaluated and upgraded to 0.67g Housner includes:
- 1. All safety-related structures
- 2.
NSSS components
- 3. Reactor coolant pressure boundary
- 4.
Safe shutdown systems
- 5.
Accident mitigation systems For the above systems and equipment the program includes:
- 1. Piping
- 2.
Equipment and valves
- 3.
Instruments
- 4.
Backup nitrogen for air operated valves
- 5.
Electrical raceways
- 6.
Loose soils resolution
- 7. Control room ceiling and HVAC
PLAN FOR EARLY RETURN TO POWER SAN ONOFRE UNIT 1.
General Provisions I.
Structures and systems whose-failure could cause an accident will be available following a 0.67g earthquake.
II. Structures and systems required to get to a safe cold shutdown will be available following a 0.67g earthquake.
III. Structures and systems not required to get to a safe cold shutdown will be deferred.
E. Structures and systems whose failure could cause an accident will be available following a 0.67g earthquake.
Structures o Containment o
Reactor Building o Turbine Pedestal o Turbine Building -
North, West and East Extensions*
Systems o Reactor coolant loop o NSSS components o All piping connected to reactor coolant loop up to first isolation valve o Main steam and steam blowdown.piping o Main feedwater piping Requires resolution of pipe reaction loads. Will pursue evaluation of the overall structural capacity of the structure and individual capacities of structural members.
II. Structures and systems required to get to a safe cold shutdown will be available following a 0.67g earthquake.
Structures o Control Administration Building o Reactor Auxiliary Building o Intake Structure o Fuel Storage Building o Seawall o Ventilation Equipment Building**
Systems o Charging, including a source of borated water detailed analysis of RWST backup piping from spent fuel pool, including assurance of integrity of spent fuel pit cooling piping o Component cooling
- Requires resolution of loose soils
-2 o Saltwater cooling two temporary 6" lines pump manufacturer indicates bearing flush water not required o Auxiliary feedwater new auxiliary feedwater tank new suction piping modification to auxiliary feedwater pump foundations to resolve loose soils bearing cooling water to turbine driven pump o
Residual heat removal o Control room ceiling o Vent stack o
Above systems include pressure boundary piping, equipment, valves and instruments
-3 o
Backup nitrogen for atmospheric dump valves (CV 76, 77, 78, 79) charging and auxiliary pressurizer spray valves (CV 304, 305) saltwater cooling pump dishcharge valves (POV 5, 6) turbine driven auxiliary feedwater pump steam supply valve (CV 113) auxiliary feedwater pump flow control valves (PCV 2300, 2301, 2302) gland seal steam supply-isolation valve (CV 96) safety injection recirculation -
reactor coolant pump seal valves (FCV 1115 D, E, F) residual heat removal heat exchanger and flow control valves (TCV 601A, 601B, HCV 602)
III. Structures and systems not required to get to a safe cold shutdown will be deferred.
Structures o South turbine building extension Basis:
failure will not impact ability to attain safe cold shutdown Systems o Safety injection o SIS recirculation o Containment spray o Containment isolation valves and penetrations o Hydrazine addition o Main feedwater pumps and lube oil cooler fan
-2 o Backup nitrogen will not be provided for feedwater pump mini-flow valves (CV 36, 37)
PORVs and PORV block valves (CV 530, 531, 545, 546) safety injection pump recirculation valves (CV 87'A, 875B) o Loose Soil Fixes refueling water pump saltwater cooling lines electrical duct to tsunami gate pipe supports in Area 14 if piping can satisfy stress criteria o Above systems include piping, equipment, valves and instruments; except where it is required as part of safe shutdown systems Basis:
Reactor coolant pressure boundary, main steam piping and main feedwater piping will be available, therefore an earthquake will not cause an accident o Electrical Raceways -
completion of modifications Basis:
Electrical raceways have not experienced failure in testing
PLAN FOR EARLY RETURN TO POWER SAN ONOFRE UNIT 1 Program for NRC Approval o
Maintain dialogue on specific aspects o
Meetings to discuss details - week of March 7 o
Submittal of plan - week of March 14 o
Meeting to discuss details - week of March 21 o
NRC approval of plan details - week of March 28 JLR:7120
ENCLOSURE 2 FEBRUARY 17, 1983 MEETING AGENDA I.
INTRODUCTION II.-. COMBINATION OF SEISMIC ANCHOR MOVEMENT AND INERTIA RESPONSES OF PIPING III.
SEISMIC ANCHOR MOVEMENT STRESSES IV. EFFECTS OF SPHERE ENCLOSURE BUILDING ON REACTOR BUILDING
METHODS FOR COMBINATION OF SEISMIC ANCHOR MOVEMENT AND SEISMIC INERTIA RESPONSES OF PIPING o
DISPLACEMENT OF ADJACENT INDEPENDANT STRUCTURES USED FOR DEVELOPING SEISMIC ANCHOR MOVEMENT LOADS AND STRESSES o
LOADS DUE TO INDEPENDANT SEISMIC RESPONSES OF ADJACENT PIPES ON COMMON SUPPORTS o
LOADS DUE TO INDEPENDANT SEISMIC RESPONSES ON EACH SIDE OF AN ANCHOR, ABSOLUTE SUMMATION:
0 SEISMIC ANCHOR MOVEMENT AND SEISMIC INERTIA LOADS o
SEISMIC ANCHOR MOVEMENT AND SEISMIC INERTIA STRESSES
ACCEPTANCE CRITERIA FOR SSE SEISMIC ANCHOR MOVEMENT STRESSES o
INCLUDED IN EQUATION 9 IF OMITTED FROM EQUATION 10 OR 11 o
EQUATION 9 ALLOWABLE LIMITED TO:
1,8SH FOR CLASS.1 2A4SH FOR CLASS 2/3 o
IF LIMITS OF EQUATION 9 ARE EXCEEDED DUE TO THE INCLUSION OF SSE SEISMIC ANCHOR MOVEMENT (SAM)
STRESSES AN AUGMENTED CLASS 2/3 EVALAUTION WILL BE PERFORMED.
EQUATION 9 FROM NC-3652 o +.75 MA + MB-
, KSH, EQ. 9 4TN z
MA = RESULTANT MOMENT LOADING ON CROSS SECTION DUE TO SUSTAINED LOADS MB = RESULTANT MOMENT LOADING ON CROSS SECTION DUE TO OCCASIONAL LOADS. FOR EARTHQUAKE. USE ONLY ONE HALF THE RANGE.
K =1.8 FOR CLASS 1 EVALUATED USING CLASS 2 RULES 2.4 FOR CLASS 2/3 NOTE:
MB = MB (SSE SI)I + 1MB (SSE SAM)t WHERE SSE SI = SSE SEISMIC INERTIA SSE SAM = SSE SEISMIC ANCHOR MOMEMENT
AUGMENTED CLASS 2/3 METHOD o
MAXIMUM INTENSIFIED STRESS RANGE WILL BE CONSERVATIVELY LIMITED TO 100 KSI o
THERMAL STRESSES WILL MEET THE REQUIREMENTS OF EQUATION 10 OR 11 o
SEISMIC INERTIA STRESSES WILL MEET THE REQUIREMENTS OF EQUATION 9
AUGMENTED CLASS 2/3 METHOD o
CALCULATION OF INTENSIFIED STRESS RANGE Eis LIMIT SwT + SLP + STH + SSSE + SSSE 100 KSI SI SAM SWT + SLP + 2 (SSSE + SSSE) 100 KSI SI SAM WHERE:
SWT = WEIGHT STRESS SLP = LONGITUDINAL PRESSURE 'STRESS STH = THERMAL STRESS RANGE SSSE = SSE SEISMIC INERTIA STRESS, 1/2 STRESS RANGE Si (MODIFIED TO INCLUDE FULL J. )
SSSE = SSE SEISMIC ANCHOR MOVEMENT STRESS, SAM 1/2 STRESS RANGE (USING FULL 2 )
EXPLANATION OF SEISMIC ANCHOR MOVEMENT CRITERIA
AUGMENTED CLASS 2/3 METHOD o
USING THE MARKL S-N CURVE, APPROXIMATELY 100 MAXIMUM STRESS CYCLES ARE AVAILABLE AT THE 100 KSI STRESS LEVEL o
LIMITING THE INTENSIFIED STRESS RANGE TO 100 KSI ASSURES THAT THE CUMULATIVE USAGE FACTOR WILL BE LESS THAN 1.0 BECAUSE THERE ARE LESS THAN 100 MAXIMUM STRESS CYCLES DUE TO THE EARTHQUAKE o
EQUATION 9 WITH INCLUSION OF SSE SAM HAS BEEN SHOWN TO AUTOMATICALLY SATISFY THE REQUIREMENTS OF THE AUGMENTED CLASS 2/3 METHOD (EVEN WITH THE 100 KSI INTENSIFIED STRESS RANGE LIMIT)
NUMBER OF CYCLES 10 102 103 104 105 10 10 CLASS 1 DESIGN PATIGJE CURVE, REDUCED
]Y K FOR A106 GrB MATERIAL.
I
-.i..
VALUES CLASS 1 DESIGN FATIGUE CURVE OF Sa (KSI)
CLASS 213 tQUTIN (l1):
IM 102 II__
oII I
I II o
c a
o
('4 iI 0
o Mark1 FATIGUE CURVE COMPARISON OF AUGMENTED CLASS 2/3 FATIGUE LIMITS WITH CLASS 1 DESIGN FATIGUE CURVE
AUGMENTED CLASS 2/3 METHOD o
VERIFICATION THAT LIMITING THE INTENSIFIED STRESS RANGE TO 100 KSI ASSURES A CUMULATIVE USAGE FACTOR OF 1.0 OR LESS o
PER SRP 3.7-3 NUMBER OF MAXIMUM STRESS CYCLES DUE TO EACH EARTHQUAKE is 10 EVENT S
N N
D= N NORMAL OPERATING 30,000 36,327 7,000
.19 SSE EARTHQUAKE 100,000 100 10
.10 CUMULATIVE USAGE FACTOR
=
.29 N
EVENT S
N N
D= N NORMAL OPERATING 30,000 36,327 7,000
.19 SSE EARTHQUAKE 100,000 100 60
.60 CUMULATIVE USAGE FACTOR =
.79
ACCEPTANCE CRITERIA FOR SSE SEISMIC ANCHOR MOVEMENT STRESSES USE OF AUGMENTED CLASS 2/3 METHOD BUT CONSERVATIVELY LIMITING THE MAXIMUM INTENSIFIED STRESS RANGE TO 100 KSI IF SSE SAM STRESS IS INCLUDED IN EQUATION 9 THE REQUIREMENTS OF THE AUGMENTED CLASS 2/3 METHOD ARE AUTOMATICALLY SATISFIED USAGE FACTORS NEED NOT BE CALCULATED SINCE LIMITING THE MAXIMUM INTENSIFIED STRESS RANGE TO 100 KSI PROVIDES FOR APPROXIMATELY 100 MAXIMUM STRESS CYCLES
EFFECTS OF THE SPHERE ENCLOSURE BUILDING ON THE REACTOR BUILDING RESPONSE
PURPOSE
- TO DEMONSTRATE THAT THE PRESENCE OF THE SPHERE ENCLOSURE BUILDING WILL DECREASE THE SEISMIC RESPONSE OF THE REPRESENTATIVE NSSS SUPORT LOCATIONS THIS WILL BE ACHIEVED BY SHOWING
- RESPONSE CONTRIBUTION OF STRUCTURAL MODE SHAPES ARE REDUCED
- RESPONSE FREQUENCIES ARE NOT SIGNIFICANTLY ALTERED
TABLE 1. DYNAMIC CHARACTERISTICS OF MODELS a)
FREQIJENCIES Horizontal Vertical N/o S.E.B*
w S.E.B w/o S.E.B w
S.E.8 3.81 3.21 4.35 3'. 94 2
6.20 4.81 14.01 6.67 3
10.71 7.70 21.06 10.78 b)
PARTICIPATION FACTORS No PF
% Total*
PF X Total PF 7 Total FF
% Total 1
21.11 69.20 24.26 58.93 15.71 89.12 19.08 83.33 2
-7.03 23.04 10.99
-26.69 0.97 5.49 1.08 4.73 3
1.42 4.67 3.20 7.78 0.18 1.01 1.67 7.31
- North-South values are given. Fast-West values are practically identical.
- Percent total values describe the modal contributions.
I0 so MODEL SRP MODEL FIGURE 1. FIRST HORIZONTAL MODE SHAPE
S EB MODEL SRP MODEL FI6URE 2.
SECOND HORIZONTAL MODE SHAPE
I I
FIRST VERTICAL MODE SHAPE
SDR MODEL SRP MODEL FIGURE 4. SECOND VERTICAL MODE SHAPE
FREQUENCIES, MODE SHAPES, PARTICIPATION FACTORS
- FUNDAMENTAL FREQUENCIES SHIFT TOWARD THE LOWER FREQUENCY SIDE BY AN AVERAGE OF ABOUT 10 PERCENT
- THE SECOND MODE IS BASICALLY A MODE ASSOCIATED WITH THE SPHERE ENCLOSURE BUILDING
SPER ENCL OSUP..d c
I~N TENA 1-S (SR,8 SE 52VO~aZ POIV7s)
TABLE.2 RESPONSES OF THE REPRESENTATIVE NSSS SUPORT LOCATIONS WITH AND WITHOUT TIHE SPHERE ENCLOSURE BUILDING SEISMIC DISPLACEMENT (INCHES)
SEISMIC ACCELERATION (g's)
NODE LOCATION NUMBER DESCHI I PT I ON EAST -
WEST NORTH -
SOUTH EAST WEST NORTH SOUTH WI thout With WI thout Wi th WI thou t WI th WI I hout With Wit hoit With Enclosure Enclosure Encl.
End.
Inc 1.
Enc.
Encl.
Eic 1.
Encl.
Encl.
Building Building Bldg.
Ridg.
hIdg.
Bldg.
B.Idg.
Bldg.
Bldg.
Bldg.
99 (A) 96 Operat-Ing 1.2960 1.0524 1.2444 1.0524 1.7686 1.1618 1.8528 1.1618 53 (B) 64 P'riry
.7776
.6648
.7560
.6648 1.0851
.8186 1.1447
.8186 Shield 88 (C) 107 Fousn(aislons
.7848
.6984
.7644
.6984 1.08(0
.8339 1.1516
.8319
TABLE 3:
FIRST MOI)r RESPONSiE TO HORIZONTAL EXCITATION:
PERCENT OF TOTAL ISPLACEMENT A
RadIial Vertical I(adLal.
Vertical Radial Vertical a) With Sphere Enclosure 98.1 98.5 91.7 98.8 95.2 97.9 BuI Iding h)W I (hout Sphere 00.0 97.8 99.7 9H.4 99.81 97.4 Bui lding*
North-South value; are given.
TABLIE 5:
FIRST MODE RESPONSE TO VERTICAL EXC 1TATION:
PERCENT OF TOTAl. 1I) ILACEMlKN'rS A
I C
Vertical Vcrt Ical Verttlcn a)
With Sphere Enclosure 100.0 100.0 Building b)
Wi thou t Sphere Enclosire 100.0 100.0 100.0 Building
-TABLE 4:
FIRST MODE RESPONSE TO HORIZONTAL EXCITATION:
PERCENT OF TOTAL ACCELERATiON A
B C
Radial Vertical Radial Vertica.
Radial Vertical a) With Sphere Enclosure 91.0 80.8 76.8 83.7 81.0 80.6 Buil ding b) Without Sphere 9.8 87.9 97.7 90.0 98.4 86.5 Building
- North-South valuiei are given.
TABLE 6:
FIRST MODE RESPONSE TO VERTiCAl.
EXCITAT[ON:
PERCENT OF TOTAL ACCEILEHATION A
C Vers I I
Ver I Ia I Vert I cid a)
Wi th Sphere Enclosure 99.3 99.1 99.9 Buil ding b) Without Sphere Enclosure 99.9 99.9 100.0 Bu ildin
CONTRIBUTION OF THE FIRST MODE A. DISPLACEMENTS
- FOR VERTICAL :
100 PERCENT
- FOR HORIZONTAL :
ABOVE 93 PERCENT B. ACCELERATIONS
- FOR VERTICAL :
99 PERCENT
- FOR HORIZONTAL:
ABOVE 97 PERCENT WITHOUT SPHERE ENCLOSURE BUILDING ABOVE 76 PERCENT WITH SPHERE ENCLOSURE BUILDING
- FIRST MODE FREQUENCIES, CORRESPONDING TO THE REACTOR BUILDING AND THE CONTAINMENT SPHERE, ARE DOMINANT WITH OR WITHOUT THE SPHERE ENCLOSURE BUILDING
TABLE 7:
PERCENT CHANCE IN REPRI'ESNTATIVE NSSS SUPPORT LOCAT IONS DUE TO CONSIDERATION OF PHERE ENCLOSURE BUTIDING DI SPLACEMENT ACCELERATION LOCATION NODE DESCRIPTION EAST -
WEST NORTH SOUTH EAST WES'r NORTH -
SOUTh (A)
Operating
-18.13
-15.4
-34.3
-37.3 Deck (B)
Primary
-14.5
-12.1
-24.6
-28.5 Shield (C)
Foundation
-11.0
-H.6
-23.2
-27.6 Note:
(-)1Indicaten Decre;aSe In Renponse
PERCENT DECREASE IN RESPONSES
- DISPLACEMENTS DECREASE BY ABOUT 13 PERCENT
- ACCELERATIONS DECREASE BY ABOUT 29 PERCENT
SUMMARY
- FUNDAMENTAL FREQUENCIES ARE LOWERED BY ABOUT 10 PERCENT
- DOMINANT RESPONSES ARE DUE TO THE FIRST FUNDAMENTAL HORIZONTAL AND VERTICAL FREQUENCIES OF REACTOR BUILDING AND CONTAINMENT SPHERE
- DISPLACEMENT AND ACCELERATION RESPONSES OF INTEREST WILL DECREASE BY 10 TO 30 PERCElT
CONCLUSIONS
- THE BASIC SINGLE MODE RESPONSE CHARACTERISTIC OF THE REACTOR BUILDING WILL NOT BE ALTERED.
STRUCTURAL RESPONSES OF INTEREST WILL DECREASE.
THEREFORE
- THE PREVIOUSLY REPORTED MINIMUM SURPLUS MARGINS WILL BE GREATER DUE TO THE INTERACTION EFFECTS OF THE SPHERE ENCLOSURE BUILDING
IT IS NOT NECESSARY TO PERFORM ADDITIONAL TIME HISTORY ANALYSES BECAUSE THE MARGINS DUE TO THE PRESENCE OF THE SPHERE ENCLOSURE BUILDING, IN ADDITION TO THE OTHER MARGINS UNIQUE TO THE REACTOR BUILDING AND NSSS ANALYSES, ARE SUFFICIENT.