ML18018A803
| ML18018A803 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 09/19/1983 |
| From: | Mcduffie M CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18018A805 | List: |
| References | |
| LAP-83-429, NUDOCS 8310130240 | |
| Download: ML18018A803 (10) | |
Text
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h.Fq REGULATORY FORMATION DISTRIBUTION SY:M (RID I
ACCESSION Nt3R: 83 1 0 1 30240 DOC, DATE: 83/09/19 NOTARIZED:
NO FACIL:50-000 Shearon Harris Nuclear Power Planti Unit fi Carol 50-401 Shearon Herr is Nuclear Power Planti Unit 2i Carol AUTH~ NAME AUTHOR AFFILIATION MCDUFFIEiM AD Carolina Power 8 Light Coo RECIP NAME REGIS IENT AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulationi Directo
$ )
DOCKET ina 05000400 ina 05000401
SUBJECT:
Forwards addi info in response to draft SER Open Item 354i including Mechnical Engineering Branch questions in 830819 8
DISTRIBUTION CODE:
8001S COPIES RECEIVED:LTR ENCI +
SIZE; ~~
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 8, Related Correspondence NOTES:
RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA INTERNALS ELD/HDS1 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 2Q NRR/DHFS/HFEBAO NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DS I/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DSI/RSB 23 RGN2 EXTERNAL: ACRS 4f DMB/DSS (AMDTS)
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28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DS I/CSB 09 NRR/DS I/METB 12 NRR/DS 22 04
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CPKL Carolina Power 8 Light Company SEP I 9 )S83 SERIAL:
LAP-83-429 Mr. Harold R. Denton,,'Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS.
1 AND 2 DOCKET NOS. 50-400 AND 50-401 RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION
Dear Mr. Denton:
Carolina Power
& Light Company hereby transmits one original and forty copies of Lhe response to Draft Safety Evaluation Report Open Item No.
354.
This Open Item includes thirty two (32) Mechanical Engineering Branch Questions transmitted by NRC letters dated August 19 and August 25, 1983.
We will be providing responses to other requests for additional information shortly.
Yours very truly, M. A. McDuffie Senior Vice President Nuclear Generation FXT/lcv (7920FXT)
'nclosure cc:
~ Mr. B.'C. Buckley (NRC)
Mr.
G.. F. Maxwell (NRC-SHNPP)
Mr. J.
P., O.'Reilly (NRC-RII)
Mr. Travis, Payne (KUDZU)
Mr.. Daniel F. Rea'd (CHANGE/ELP)
Mr. R.
P. Gruber (NCUC)
Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Mr. John D. Runkle Dr. Richard D. Wilson Mr. G.'. Bright (ASLB)
Dr. J.
H. Carpenter (ASLB)
Mr. J. L. Kelley (ASLB) 8310130240 830919 PDR ADOCK 05000400 E
PDR 411 Fayetteville Street
~ P. O. Box t551
~ Ratetgh, N. C. 27602
ri
/
V I
Shearon Harris Nuclear Power Plant Draft SER Open Item No.
354 NRC Ouestion 210.47 Pum Nozzle Loads The Design Specification CAR-SH-M-13, Rev. 8, dated 5/4/83 (6.1) says that in no case shall the acceptable reactions due to thermal loading plus the seismic loading be lower than:
Mr ~ 250 SM where M
resultant moment in any direction, ft-lb SM section modulus of metal pipe connected to pump nozzle, cu in.
The Specification (6.3) indicates that SM is for Schedule 40 pipe; hence, for the 14-inch nozzle:
Mr 250 x 12 x 61.4 184,200 in-lb of 28,920 in-lb.
(a)
Explain the seeming discrepancy where the Specification requires a
minimum 14-inch nozzle load capacity of M 184,200 in-lb; whereas the Stress Analysis uses about one-sixth of tlat moment as the maximum load acceptable to the pump manufacturer.
(Also see 0210.66)
The Seismic Stress Analysis ME-529 dated 4/14/78 for the Service Nater Booster Pump (Model 3405L) (4.2) cites a maximum resultant moment for the 14" Section
RESPONSE
Paragraph 6.1 (Part-II) of Specification is a general requirement for the equipment nozzle load.
The nozzle loads specified are based upon a proportion of the pipe allowable stresses, which conservatively insures structural integrity of the piping system and avoids excessive deformation to the connecting equipment.
This paragraph is imperative during the equipment contract evaluation phase of the prospect.
In this, case, manufacturer (Goulds) had taken exception during the bid phase, (see attached proposal dated 3/20/1973),
from the Ebasco specified nozzle loads.
Manufacturer has indicated that their acceptable nozzle loads in the stress report (see attached ME-529 Add.
page 13, paragraph 4.2).
Based on manufacturer's acceptable nozzle loads, Ebasco is checking piping design system load requirements against manufacturer's acceptable load.
Eventually, piping system shall be designed to mutually acceptable nozzle loads between manufacturer and Fbasco.
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YiE-529 P,dA. 1 g.li. 8 l 4.2 nozzle Loads The Maximum Nozzle loads are tabulated belov for this pump, vhich has a 14" suction and a 12" discharge.
These nozzle loads per Goulds Pumps
~ Inc.
and are:
12" Dischar e
14" Suction Resultant Force, Lbs.
Components Fx, Fy> Fz, lbs.
2, 000 1, 155 2,000 1,155 Resultant Moment, In-lbs.
28,920 28,920 Components Nx, Ny, Nz, in-lbs.
16,697 16,697 The forces and moments are transferred to the pump impeller centerline for the static analysis.
The computer output is given in hpp. h.
The computer input is included on page 14.
4.3 -Internal Pressure Loading 0
The internal pressure design conditions are 225 psig at 140 F.
4.4 Shaft Torsional Loading The motor horsepover is 200 at 1780 R.P.N.
6300D~200 1780 Thus, the max. torque is:
7,079 in-lbs.
4.5 Other Pump Normal Loads The -pump is sub)ected to a 211 lbs. radial and a 500 lbs. 'axial load on the impeller during normal operation.
Shearon Harris Nuclear Power Plant Draft SER Open Item No.
354 NRC Ouestion 210.48 Pum Seismic Loads The Design Specification CAR-SH-?f-13, Rev. 8, dated 5/4/83 (Attachment No. 5, 4.1) says that "Static coefficients will be furnished to the Seller at a later date."
The Seismic Stress Analysis HE-529 dated 4/14/78 (4.1) says "The seismic loadings applied exceed those given by the specification Explain how the statement in the Stress Analysis could be made in view of the seeming absence of static coefficients "by the specification."
RESPONSE
Pump assembly frequency has been determined by using frequency analysis.
In applying the frequency analysis the following steps were talcen:
(a)
Develop dynamic model.
(b)
Compute resonance frequencies (by computer analysis ICES-STRUDL program).
(c)
Frequency excess 33 Hertz, therefore, equipment is rigid (pump assembly frequency is 41.5).
(d)
Then use floor response spectra curves.
(These curves are part of the specification for the specific floor level RAB 236').
Therefore, static coefficient does not apply for the frequency analysis.
(7876FXTccc)
Shearon Harris Nuclear Power Plant Draft SFR Open Item No.
354 NRC Ouestion 210.49 Pump Pressure Boundary Integrity (a)
What checks were made of the pressure boundaries of the centrifugal pump; e.g.,
of the casing bolts?
(b)
The Design Specification CAR-SH-H-13, Rev. 8, dated 5/4/83 (9.1) says that "Shop hydrostatic shall be made on all pump casings."
What was the hydrostatic test pressure and why is it not specified in the Specification?
Provide a copy of the NPV-1 data report applicable to the pump covered by the Stress Analysis HE-529 dated 4/14/78.
RESPONSE
(a)
Hydrostatic test has been performed on the pressure boundaries of the pump as per Goulds'rocedure OCP No.
120 (attached).
(b)
Hydrostatic test shall meet the requirements of the ASHE Boiler and Pressure Vessel
- Code,Section III and test pressure at no less than one and one half (1 1/2) times design pressure.
Pump design pressure is indicated on specification Part
- One, Page 5, paragraph 6.13.
The NPV-1 data report is attached.
(7876FXTccc)