ML18018A734
| ML18018A734 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/02/1983 |
| From: | Mcduffie M CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| LAP-83-401, NUDOCS 8309090512 | |
| Download: ML18018A734 (8) | |
Text
REGULATORY ORthATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR-8309090512 DOC.DATE: 83/09/02 NOTARIZED:
NO FACIL:SO-400 Shearon Harris Nuclear Power Planti Unit 1E Carolina 50-401 Shearon -Harris Nuclear Power Plants Unit 2i Carolina AUTH.NAthEr AUTHOR AFFILIATION MCDUFFIEPM.A.
Car ol ina Power 8 Liaht Co RKCIP. NAME REC IP IEtjT AFFILIATION DENTONPH.R.
Office of Nuclear Reactor Reaulations Director I
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SUBJECT:
Forwyrds rev to docUment control Procedure es described ip Section 17.2 of FSAR.FSAR will be chanced in next
- amend, DISTRIBUTIDN coDE: Boots coPIES RECEIVED:LTR ~nE ENcL g SIZEi TITLE: Licenslno submittal:
psAR/FBAR Amdts
& Related oopnespondence f40TES:
DOCKET Q5000400 05000401.
RECIPIENT ID CODE/NAME NRR/Dl /ADL NRR LB3 LA INTERNAL: ELD/HDS1 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB li
'NRR/DE/EQB 13 NRR/OE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFKB40 NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/OS I/CPB 10 NRR/DSI/ICSB 16 t4RR/DSI/PSB 19 NRR/DSI/RSB 23 RGN2 EXTERNAL: ACRS 41 DMB/DSS (AthDTS)
LPDR 03 NSIC 05 COPIES LTTR ENCL 1
0 1
0 1
0 3
3 1
1 1
1 2
2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 3
3 6
6 1
1 1
1 1
RKCIP IENT ID CODE/NAME NRR LB3 BC BUCKLEYPB 01
'IK'ILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DK/GB 28 NRR/OE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DSI/ASB NRR/DSI/CSB 09 NRR/DSI/METB 12 NRR DSI RAB 22 FILE 04 I/MIB BNL(AMDTS ONLY)
FEMA>>REP DIV '39 NRC'PDR 02 NTIS
- COPIES LTTR ENCL 1
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2 2
1 1
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TOTAL NUMBER OF COPIES REQUIRED:
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Carolina Power & Light Company SEP 03 3983 SERIAL:
LAP-83-401 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 DOCUMENT CONTROL PROCEDURES
Dear Mr. Denton:
Carolina Power 6 Light Company hereby documents a revision to the Shearon Harris Nuclear Power Plant (SHNPP)
Document Control Procedure as described in Section 17.2 of the Pinal Safety Analysis Report (PSAR).
One original and forty copies are transmitted for the use of the NRC.
Attachments 1 and 2 show the revision to the Procedure to reflect the present method of working at the Harris site.
The FSAR will be changed as shown in the attachments in the next FSAR amendment.
Yours very truly, M. A. McDuffie Senior Vice President Nuclear Generation MAM/ccc (7783PXT)
Attachment cct 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.. Read (CHANGE/ELP)
Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB)
Dr. J.
H. Carpenter (ASLB)
Mr. J. L. Kelley (ASLB) r 8309090512 830902 PDR ADOCK 05000400 A
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411 Fayetteville Street
< P. O. Box 1551 o Raleigh, N. C. 27602
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ATTACHMENT 1 Revision to SHNPP Document Control Procedure The change to the procedure is described in the following paragraph which will be inserted into page 17.2.6-2 of the SHNPP FSAR as shown on Attachment 2.
INSERT Verification that the plant meets design or that a system meets design occurs progressively and sequentially throughout the construction and inspection process.
The QA program describes a system that inspects components and processes in accordance with predetermined hold points described in formal procedures.
Final certification of construction as meeting the design requirements will be made after review of the documentation, walk downs and preoperational testing which will occur prior to Fuel Loading except as may be mutually agreed to by CPSL and the NRC.
Once the plant is operational, systems will be implemented to assure installed plant modifications conform to design.
(7783FXTlcv)
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SHNPP FSAR As-built documents currently are being produced under the engineering procedures of Ebasco Services and therefore, under the Ebasco QA program.
As engineering documents are transferred to CP&L for maintenance they will be covered under CP&L engineering procedures and thereby the CP&L Quality Assurance Program.
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Procedures exist within the Construction organization and the Engineering organization such that changes by asso'ciation with the original
'design documents become the as-built design for the plant.
The timeliness of revision of drawings is currently controlled by Ebasco engineering procedures and will in the future be controlled by CP&L procedures.
(Add the INSERT as a new paragraph)
- 17. 2.6-2 Amendment No.