ML18018A521

Forwards Responses to Draft SER Open Items 34,35,40,42 & 44

ML18018A521
Person / Time
Site:	Harris
Issue date:	05/04/1983
From:	Mcduffie M CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
LAP-83-125, NUDOCS 8305060555
Download: ML18018A521 (16)

Text

REGULATOf INFORMATION DISTRIBUTION

'TEM ('BIDS)

'ACCESSION NBR:8305060555 DOC ~ DATE: 83/05/04 NOTARI'ZED:

NO FACIL:50-400 Shearon garris Nuclear Power.Planti Uni,t li 'Carolina 50-401 Shearon Harris Nuclear Power Planti Uni;t 2i ',Carolina AUTH,NAME AUTHOR AFFILIATION MCOUFFIEi M + A.

Carol ina'Power 8 Light Co+

RECIP,'NAME RECIPIENT AFFILIATION DENTONeH+R ~

Office of Nuclear Reactor Regulationi Director

SUBJECT:

Forwards responses,to draft SER Open Items -34g35i40i42 8

.DISTRIBUTION CODE:

B001S

<<COPIES ~RECEIVED:LTR.

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.'ITLE:

Licensing Submittal i.PSAR/FSAR Amdts 8 Related Cor respondence NOTES:

DOCKET 05000400 05000401 RECIPIENT IO CODE/NAME NRR/DL/ADL NRR LB3 LA INTERNAL: ELO/HDS1 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB li NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/OS I/AE8 26 NRR/DSI/CPB 10 NRR/OS I/ICS8 16 NRR/OSI/PSB 19 NRR/OSI/RSB 23 RGN2 EXTERNAL: ACRS 41 DMB/DSS (AMDT'S)

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LAP-83-125 Carolina Power 8 Light Company

>AY 04 l9B3 gt I

Mr. Harold R. Denton, Directo'r 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 DRAFT SAFETY EVALUATION REPORT RESPONSES MATERIALS ENGINEERING BRANCH

Dear Mr. Denton:

Carolina Power

& Light Company (CP&L) hereby transmits one original and forty copies of the responses to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER)

CP&L Open Item Nos.

34, 35, 40, 42, and 44 (Attachment I).

Carolina Power

& Light Company will be providing responses to other Open Items in the DSER shortly.

Yours very truly, PS/pgp (6703PSA)

Attachment M. A. McDuffie Senior Vice President Engineering

& Construction CC:

Mr. N. Prasad Kadambi (NRC)

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

Mr. J.

P. O'Reilly (NRC-RII)

Mr. Barry J. Elliot (NRC-MTEB)

Mr. Travis Payne (KUDZU)

Mr. Daniel F.

Read (CHANGE/ELP)

Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Ms. Patricia T. Newman Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB)

Dr. J.

H. Carpenter (ASLB)

Mr. J. L. Kelley (ASLB) 8305060555 830504 i

PDR ADOCK 05000400 E

PDR fSgt 411 Fayetteville Street

+ P. O. Box 1551 o Raleigh, N. C. 27602

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ATTACHtKNT I.

Response

to Open Itera Vivos. 34, 35, 40, 42, and 44

OPEN ITEtf NO. 34 (DSER Section 5.3.1, page 5-1)

The applicant must identify whether SA-540, Class 1 or 2 material was used for closure bolting in reactor coolant pumps.

RESPONSE

TO OPEN ITEN NO.

34 The reactor coolant pump main flange bolts are SA-540, Grade 824, Class 4.

The seal housing bolts are SA-139, Grade B7.

Table 5.2.3-1 in the FSAR will be updated to reflect this.

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0 en Item f35 Indicate whether the individuals performing the fracture toughness test were qualified by training and experience and whether their competency was demonstrated in accordance with a written procedure.

If-the above infor mation cannot be provided, state why the information cannot be provided and identify why the method used for qualifying individuals is equivalent to those nf Paragraph III.B.4 Appendix G, 10 CFR 50.

(SEC:

5.3. 1)

Response

to Open Item F35 The Shearon Harris Unit 1 Nuclear Station reactor vessel was fabricated to ASME Code Section III requirements in effect prior to the issuance of IOCFR 50, Appendix G.

However, the intent of Appendix G requirements is satisfied since Chicago Bridge and Iron met the requirements of HA-4220 by schooling and training of personnel performing fracture toughness tests; and trained and qualified personnel supervised all testing.

OPEN ITEM ¹40:

Revise the FSAR to indicate that the conclusions of Westinghouse Topical Report WCAP-9292 are applicable to Harris SA-533 Grade A, Class 2 steel and SA-508 Class Za steel.

(SEC:

5.3. 1)

RESPONSE

TO OPEN ITEM ¹40:

WCAP-9292 demonstrates the acceptability of SA-508 Class 2a and SA-533A Class 2 steels on a generic basis for use in reactor coolant pressure boundary applications.

Applicability of this report to Shearon Harris is documented in FSAR Section 5.2.3.

(See Reference Section 5.2.3. 1.)

0 en Item 842 To demonstrate the surveillance capsule program comolies with Paragraph II.C.3 of Appendix H:

(SEC:

5.3.3) a.

Provide the withdrawal schedule for each capsule.

b.

Provide the lead factors for each capsule.

c.

Indicate the estimated reactor vessel end of life fluence at the inside

diameter, I/4 wall, and 3/4 waII thickness for each reactor vessel beltline material.

Response

to Open Item 842 Ca sule Withdrawal Schedule for Shearon Harris Units I and 2

Capsule Iden.

Vessel Location Lead Factor klithdrawal Time EFPY)

Est imated Capsule Fluence (n/cm

)

343'07'87'IOo 290o340'.5 3.5 3.5 2.9 2.9 2.9 1st Refueling 3

6 11 20 Standby 0 8 x 10 "

1.9 x

10 3.7 x

10 5.7 x 10 1.0 x 102 Estimated End-of-Life Fluence Vessel Inside Diameter - 5.7 x

10 n/cm-19 Vessel I/O Thickness

- 3.4 x 10 n/cm 19 2

Vessel 3/4 Thickness

- 8.4 x 10 n/cm 18

0 en Item 444 Identify the location of each material surveillance capsule and the materiaIs in each capsule.

(SEC:

5.3.3) a.

For each base metal and heat-affected zone surveillance specimen

, provide the specimen type, the orientation of, the specimen relative to the principal rolling direction of the plate, the heat

number, the component code number from which the sample was removed, the chemical composition especially the copper (Cu) and phosphorus (P) contents, and the heat treatment received by the sample material.

b.

For each weld metal surveillance specimen

p. ovide the weld identification from which the sample was removed, the weld wire type and heat identification, flux type and lot identification, weld process, and heat treatment used for fabrication of the weld sample.

c.

Provide a sketch which indicates the azimuthal location for each caosule relative to the reactor core.

Res onse to 0 en Item 844 Vnit I Surveillance Capsules Material Inter. Shell Inter. Shell Weld Metal Haz Metal Heat No.

B4197-2 B4197-2 B4197-2 Code No.

Il 2x ll-2xx AB 11-2 Number of Charnys 15 15 15 15 Number of Tensi les Number of I/2T - CTS x

Specimens oriented in the principal roIling direction xx Specimens oriented normal to the principal rolling direction Chemical composition of plate identified in Table 5.3. 1-6 Heat Treatment of Plant B4197-2 shown below 1625'F - 4Hr - water quench 1260'F - 4Hr - air cool 1150'F - 35 3/4Hr - furnace cooled Weld Metal -

Fabricated from type INMM Weld Wire Heat No.

5P5771 and Linde 124 Flux Lot No. 0342 Heat Treated at 1150'F - 10Hrs - furnace cooled.

Vnit 2 Surveillance Capsules Material Heat No.

Code No.

Number of Chl! Di's Number of Tensi les Number of I/2T - CTS Inter. Shell B4197-I Inter.

She I I B4197-1 Weld Metal Haz Metal 84197-1 11 2x 11-2xx AB 11-2 15 15 15 15 x

Specimens or iented in the principal rolling direction xx Specimens oriented normal to the principal rolling direction Chemical composition of plate identified in Table 5.3.1-9 Heat Treatment of Plant B4197-I:

shown below 1625'F - 4Hr - water quench 1260'F - 4Hr - air cool 1150'F -

413/4Hr - furnace cooled Weld Metal -

Fabricated from type INMM Weld Wire Heat No.

5P7397 and Linde 124 Flux Lot No. 0342 Heat Treated at 1150'F - 9~Hrs - furnace cooled.

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REACTOR VESSELS NEU>nO"IPAf CORE BARRB (Attachment ta Open Iten 544)

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