ML18022A403

From kanterella
Jump to navigation Jump to search
Forwards Amend 34 to FSAR for Shearon Harris Nuclear Power Plant Unit 1.Amend Provides Changes to Section 14.2 Re Preoperational Testing.Justification for Each Change Listed
ML18022A403
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 09/11/1986
From: Cutter A
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML18022A404 List:
References
NLS-86-280, NUDOCS 8609160359
Download: ML18022A403 (5)


Text

REGULA I I Y INFORNAT ON D I STR BUT 1 SYSTEt'1 ( R IDS)

ACCESSION NBR: 860926035'Ij'OC. DATE: 86/09/2 2 NOTARIZED: YES DOCKET I FACIL: 50-400 Shearon Hav v is Nucleav Power Plant> Unit 1> Carolina 05000400 AUTH. MANE, AUTHOR AFFILIATION CUTTER> A. B. Cav olina Power 8c Light Co.

RECIP. NANE RECIPIENT AFFILIATION DENTON> H. R., OFfice of Nucleav Reactor Regulation> Div ectov (post 851125

SUBJECT:

Forwards Amend 34 to FSAR For Shea&on Harris Nucleav'oeer Plant Unit 2. Amend provides changes to Section 14. 2 v e pv e-opev'ationL testing. Justification For each change l i sted.

DIBTRIDVTION CODE: BOOID COPIEB RECEIVED: LTR cO ENCL+K BIIE:

TITLE: Licensing Submittal: PSAR/FSAR Amdts Zc Related Cov v'espondence NOTES: Application Fov pevmit v enewal Filed. 05000400 RECIPIENT COPIES REC I P I ENT COPIES ID CODE/NA1'lE LTTR ENCL ID CODE/NAI'1E LTTR ENCL PMR-A EB PWR-A EICSB 2 2 PNR-A FOB 1 PNR-A PD2 LA 1 1.

PNR-* PD2 PD 1 BUCKLEY> B 01 2 2 PMR-A PSB PWR-A RSB 1 INTER NAL: ADN/LF1'1B 1 0 ELD/HDS1 0 IE FILE 2 1 IE/DEPER/EPB 36 IE/DGAVT/GAB 21 NRR BNR ADTS 0 NRR PNR-B ADTS 1 0 .L 1 NRR/DHFT/NTB 2 1 EG FIL 04 1 RGN2 3 3 ANI/Nl8 0 EXTERNAL: BNL(ANDTS ONLY) 1 DMB/DSS (ANDTS)

LPDR 03 1 NRC PDR 02 1 NSIC,, 05 1 PNL GRUEL> R 1 TOTAL NU1'1BER OF COPIES REQUIRED: LTTR 30 ENCL 25

~ ~)i);ti i)

<3

")

L'"',

)!,) $',,p ) I.">>

)1

'e>>j i "i,

"p

'1', II

'3>>

I

)'V<

6

'~')"

'lf "f,7 fT t~a 1 fQh) .,hr.t".)P v)t'r,r c

~

'uc'f Rf 4 ll' 1 I'tt )

Ul'f lt

'1

"'tl ' l t,>>h 1

I

~

hI I'

1

'II/

~ *

. << "3-." )

ill ~ .

>1'>>fp f'

! +1 I!p $ )

f)Q ':)Fh v

)I>>I

"'))f I h'g!I gt,lr

" tifr' I ) ") t,r(

'c.X i V>>i.~ '" af/g,g 'graf S, I) I

>> 1 1iyr>>f>>, <<ttt)

'.};> f"- ';v <<1 fT ) q 4") 0 f f '1' ~3ttttlA vR' "f <<ff'1>> q I 1 r F 1 tf ~

'11 ~ f

)v f)f)i bt ". J'(' f-"',"'.)th.. f -~ . "'kq "<'Yf ~ ~ 'tA'."!hij )

ft 3 ) h'f)v) 3 )'t3 '>>tf ' fN)'

1 >>~f)*0

~ 1 f I '

'!>>Itt yht "

l, 1 1 P

'V

,"v()II.

')W v)*,]"

)4!

~

Q R3N

) i.r f t vN ii) fl,li-;r, g )

'>>);II!

1 i I/ vgg ht ft >> t O f'f)

'v'> 1 ) <f "'4

>>1'1.. <<>>v "f>>ll I) <Jf >

'i 't"~ f i!g,f'

'i II vrt) 'l I

,0 ~

CNK Carolina Power 8r Light Company SERIAL: NLS-86-280 SEP IL 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 FSAR AMENDMENT NO. 30

Dear Mr. Denton:

Carolina Power R Light Company (CPRL) hereby submits Amendment No. 30 to the Shearon Harris Nuclear Power Plant (SHNPP) Final Safety Analysis Report (FSAR). This amendment provides changes to Section 10.2 concerning Pre-Operational Testing. The following provides justification for each change:

10.2.2 Revisions are made to reflect a management 10.2.3.2 change. The Start-up Power Test Program 10.2.5.2 responsibility is changed from the Manager Start-up to the Manager Technical Support.

10.2.12.1. 16 Revisions are made to reflect the current Diesel Generator Test Summary Acceptance Criteria. Technical Specifications and Pre-Operational Test Procedures require a generator load sequence of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 110 percent and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at 100 percent.

10.2. 12.1.37 Revisions are made to reflect that the setpoint for a CCW low-flow alarm is established in CPdcL Setpoint Document CAR 2166-B-508.

10.2. 12.1.60 Revisions are made concerning Process Computer Test Summary to reflect current acceptance criteria.

10.2. 12.1.62 Revisions to RWST Test Summary are made for the following reasons: Using water to simulate tank level is unnecessary as it is a repetition of transmitter calibra-tion procedure. The automatic fill valve on the RWST is replaced by a manual fill valve. RWST level setpoints are verified in loop calibration and are established in CPRL Setpoint Document CAR 2166-B-508.

86091b03'O'V 860'Pi 1 PDR *DOCK 05000400 PDR ~i 411 Fayettevilte Street ~ P. O. Box 1551 ~ Raleigh, N. C. 27602

54r. Harold R. Denton NLS-86-270 / Page 2 10.2.12.2.6 The Reactor Coolant System Flow Coastdown Test Summary is revised to reflect acceptance criteria esta-blished via the Westinghouse NSSS Start-up Manual. The Start-up Manual is used since it establishes design flow coast-down criteria at hot standby conditions which are test specific. These hot standby conditions are consistent with the LOFTRAN code analyzed at 100-percent power which is assumed in the FSAR Chapter 15 analysis.

10.2.12.2.11 The Power Coefficient Measurement Test Summary is revised to reflect that the doppler power coefficient predicted C is determined from data in the Cycle No. 1 Westinghouse Nuclear Design Report.

C is not the limiting value that is established via the safety analysis, but rather an analytical prediction that is specific to a corg configuration. The comparison of C to C validates the analytical prediction of the Nuclear Design Report. The acceptance criteria of +0.5 is a Westinghousygeneric valy that establishes a band around C which, if C falls within that band, demonstrates acceptable agreement between predicted and measured results.

10.2. 12.2.25 Revisions are made to reflect consistency with the Operations Surveillance Test for RCS Leakage Evaluation.

10.2.12.2.26 The Natural Circulation Flow Test Summary is revised to reflect the deletion of flow data due to inaccuracies in flow measurement and the use of thermocouple data for a more realistic power distribution.

10.2.12.2.31 Revisions are made to reflect the proper Steam Generator Test for Condensation Induced Water Hammer.

Each revised page bears the amendment number, and technical changes are indicated by vertical bars in the page margin. Instructions for inserting revised pages are included.

Mr. Harold R. Denton NLS-86-270 / Page 3 If you have any questions regarding this amendment, please contact me.

Your very tr l, A. B. Cutter - Vice esident Nuclear Engineering &. Licensing ABC/GB/vaw (00283DK)

Enclosure cc: Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP),

Dr. 3. Nelson Grace (NRC-RII)

Wake County Public Library A. B. Cutter, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power R Light Company.

otary S My commission expires: 5-IB R