ML18019A745
| ML18019A745 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/17/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-057, NLS-86-57, NUDOCS 8603260128 | |
| Download: ML18019A745 (15) | |
Text
REQUl ATO INFORMATION DISTRIBUTION TEM <RIDS)
ACCESSION NBR 8603260128 DOC. DATE: 86/03/17 NOTARIZED:
NO DOCKET 0 FACIL: 50-400 Shearon Harris Nuclear Power Plant> Unit'> Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION ZIMMERMAN>S. R.
Carolina Power Cc Light Co.
RECIP. NAME RECIPIENT AFFILIATION DENTON> H. R.
Office of Nuclear Reactor Regulation>
Director <post 851125
SUBJECT:
Forwards responses to five questions re FSAR Sections
- 3. 9 5
- 3. 10. Draft Table
- 3. 9. 2-1 re method of qualifiaction for NSSS equipment encl.
DISTRIBUTION CODE:
B001D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 0 Related Correspondence NOTES: Application for permit reneeel filed.
05000400 RECIPIENT ID CODE/NAME PWR-A *DTS P WR-A EICSB PWR-A PD2 LA BUCKLEY> B 01 PWR-A RSB INTERNAL: ADM/LFMB IE FILE IE/DGAVT/GAB 21 NRR PWR-A ADTS NRR ROE> M. L NRR/DHFT/MTB RQN2 EXTERNAL: 24X DMB/DSS (AMDTS)
NRC PDR 02 PNL GRUEL> R COPIES LTTR ENCL 1
1 2
2 1
2 2
1 1
1 0
1 1
1 1
1 0
1 1
1 1
3 3
1 1
1, 1
1 1
1 1
RECIPIENT ID CODE/NAME PWR-A EB PWR-A FOB PWR-A PD2 PD PWR-A PSB ELD/HDS1 IE/DEPER/EPB 36 NRR BWR ADTS NRR PWR-B ADTS T/HFIB EQ FIL RM/DDAMI/MIB BNL(AMDTS ONLY)
LPDR 03 NSIC 05 COPIES LTTR ENCL 1
1 1
1 1
1 1
0 1
0 1
0 1
1 1
1 1
0 1
1 1
TOTAL NUMBER OF COPIES REGUIRED: LTTR, 34 ENCL 28
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Carolina Power & Light Company MAR 1 7 >986 SERIAL: NLS-86-057 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.
1 - DOCKET NO.50-000 SEISMIC QUALIFICATIONREVIEW TEAM COMMENTS ON SHEARON HARRIS FSAR SECTIONS 3.9 AND 3.10
Dear Mr. Denton:
Carolina Power k Light Company hereby submits responses to five questions received informally with regard to the Shearon Harris FSAR Sections 3.9 and 3.10.
If you have any questions, please contact Mr. Pedro Salas at (919) 836-8015.
Yours very truly, PS/ccc (3383PSA)
Enclosure ager Nuclear Licensing Section CC:
Mr. B. C. Buckley (NRC)
Mr. G. Bagchi (NRC)
Mr. J. Singh (EGRG)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
Mr. Travis,Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Wake County Public Library Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Dr. 3. H. Carpenter (ASLB)
Mr. J. L. Kelley (ASLB)
Mr. H. A. Cole B~ogP601W O~OPP400 8603%7 ADOQK pgR A
411 Fayettevilte Street o P. O. Box 1551 o Raleigh, N. C. 27602
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QUESTION 1 According to the notation used in Table 3.9.2-1, all of the NSSS equipment items listed in this table were qualified by some form of analysis, while none were qualified by test.
Explain how operability was demonstrated for the equipment on this list that is structurally complex, such as )he pressurizer safety valves. Operability of this type of item would almost have to be demonstrated by test.
RESPONSE
Corrections have been made to Table 3.9.2-1 that indicate testing is the method of qualification for active valves and the centrifugal charging pump.
QUESTION 2 The emergency and faulted stress limits for NSSS supplied active pumps and valves (Tables 3.9.3-5 and 3.9.3-6) exceed yield stress.
This could result in permanent deformation in these components that may adversely affect their operability. Explain how operability can be assured at these stress levels.
RESPONSE
The emergency and faulted stress limits for NSSS supplied active pumps and valves (Tables 3.9.3-5 and 3.9.3-6) are code limits and do indeed indicate that under certain temperature and loading conditions, yield stress may be exceeded.
- However, Westinghouse equipment specifications clearly spell out that operability must be maintained under these loading conditions for both pumps and valves and static deflection tests on active valves further verify (with margins) that valves willremain operable.
In reviewing design reports for active pumps of several plants, Westinghouse has found that yield stress may be exceeded in some cases of faulted loading and specific temperature, but this was only the case at the extremities of piping flanges not on critical parts.
Yield stresses are not exceeded on active valves.
QUESTION 3 Section 3.10.2 states that the stresses calculated for safety-related motors are compared with allowable values, but does not indicate what the allowable values are.
Identify the source of allowable stresses in these components.
RESPONSE
~Com anent Motor Shaft Stator Core Welds Stator Core to Frame Welds Mounting Bolts Motor Feet Bearing Load Rotor Deflection Shaft Slope at Bearing Source for Allowable Stress Values ASA B17.C Code for transmission shafts AISC Construction Manual AISC Construction Manual ASME BRPV Code III for bolting and support ASME BdcPV Code III for bolting and support Manufacturer recommended values Allowable clearances as identified by vendor Allowable clearances as identified by vendor (3383PSA/ccc)
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QUESTION 0 Section 3.10.2.1 states that testing, analysis, or a combination of test and analysis are equally valid methods for seismically qualifying electrical equipment supplied by the NSSS vendor.
Meanwhile, Section 3.10.2.2 indicates that testing is the preferred method of qualification for electrical equipment supplied by other than the NSSS vendor.
These two qualification philosophies appear to be inconsistent.
In reality, testing is generally the recommended method for qualifying electrical equipment since functionability of much of this equipment under seismic conditions is very difficultto demonstrate by analysis.
RESPONSE
Qualification by testing is generally the preferred method; however, where justifiable, qualification by analysis is permitted.
When Westinghouse employs analysis as a qualification method, justification is provided.
QUESTION 5 Paragraph 3.10.2.1.1(a) states that the single-axis single-frequency tests that were performed in accordance with IEEE-300-1971 have been justified relative to the requirements of IEEE-300-1975.
Although the NRC has accepted this methodology for specific equipment items, it has not accepted these qualifications on a generic basis.
Verify that the NRC has specifically approved single-axis single-frequency testing for all items on which this testing methodology was used.
RESPONSE
Equipment supplied to CPRL which employs single-axis sine bent testing as the method for seismic qualification is identified below.
Solid State Protection System Nuclear Instrumentation System Instrument Bus Power Supplies Safeguards Test Cabinets The NRC has accepted this testing as acceptable for equipment qualification pursuant to the limitations delineated in the" Safety Evaluation Report issued for WCAP-8587.
(3383PSA/pg p )
SHNPP FSAR TABLE 3 ~ 9m 2 1
METHOD OF QUALIFICATION FOR NSSS E UIPMENT
~Com onent Reactor Coolant S stem Reactor Vessel CRDM Housing Seismic Steam Generator (tube side)
(shell side)
Pressurizer Reactor Coolant Hot and Cold Leg Piping, Fittings and Fabrication Surge Pipe, Fittings and Fabrication Crossover Leg Piping,'Fittings and Fabrication RTD Bypass Manifold Pressurizer Safety Valves Power Operated Relief Valves (AO~ - aA<Wt )
Valves of Safety Class 1 to Safety Class 2 Interface Pressurizer Relief Tank
~9
( actiue)
(BOA-ac+i<<)
1 Reactor Coolant Thermowell Reactor Coolant Pump RCP Casing Main Flange Thermal Barrier Thermal Barrier Heat Exchanger
//1 Seal Housing 82 Seal Housing Pressure Retaining Bolting RCP Motor Motor Rotor Motor Shaft Shaft Coupling 3.9.2>>9
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SHNPP FSAR TABLE 3.9.2-1 (Cont'd)
METHOD OF QUALIFICATION FOR NSSS E UIPMENT
~Con onent Reactor Coolant S stem (Cont )
Seismic Desi n (1)
Spool Piece Flywheel Bearing (Motor Upper Thrust)
Motor Bolting(2)
Motor Stand Motor Frame Upper Oil Reservoir (UOR)
UOR Oil Cooler Lower Oil Reservoir (LOR)
LOR Cooling Coil Lube-Oil Piping Chemical 6 Volume Control S stem Regenerative HX Letdown HX (tube= side)
(shell side)
Mixed Bed Deminerali.zer Cation Bed Demineralizer Volume Control Tank Centrifugal Charging Pump Boric Acid Blender Letdown Orifices Excess Letdown HX (tube side)
(shell side)
- 3. 9. 2-10
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SHNPP FSAR h$m TABLE 3.9.2-1 (Cont'd)
METHOD OF QUALIFICATION FOR NSSS EQUIPMENT
~Com onent Boron Rec cle S stem (Cont.)
2.
Gas Stripper r
3.
Submerged Tube Evap Seismic Desi n (1) a.
Feed Side b.
Steam Side 4.
Evaporator Condenser a.
Distillate Side b.
Cooling Water Side 5.
Distillate Cooler a.
Distillate Water Side b.
Cooling Water Side 6.
Absorption Tower 7 ~
Vent Condenser a.
Gas Side b.
Cooling Water Side 8
Distillate Pump 9.
Concentrate Pump 10.
Piping a.
Feed b.
Distillate c.
Concentrate 2
2 2
11'alves a.
Feed b.
Distillate c.
Concentrate d.
Cooling e.
Steam Z'
2 3 W 3 4'
- 3. 9. 2-13
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SHNPP FSAR t
TABLE 3.9.2-1 (Cont'd)
METHOD OF QUALIFICATION FOR NSSS EQUIPMENT Component Seismic Design
( I)
Hain Steam Main Steam Isolation Valves Liquid Waste Processing System Reactor Coolant Drain Tank Reactor Coolant Drain Tank Pump Reactor Coolant Drain Tank RX (tube side)
(shell side)
Waste Evaporator Feed Pump Waste Evaporator Package 1.
Feed Preheater a.
Feed Side b.
Steam Side 2.
Gas Stripper 3.
Submerged Tube Evaporator a.
Feed. side b.
Steam Side 4.
Evaporator Condenser a.
Distillate Side b.
Cooling 'Water Side 5.
Distillate Cooler a.
Distillate Mater Side b.
Cooling Mater Side Absorption Tower 7.
Vent condenser a.
r3as Side b.
Cooling Mater Side 3.9.2-14 Amendment No ~
2
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