ML18018B728

Forwards marked-up Tech Specs,Based on Rev 4 to NUREG-0452, STS for Westinghouse Pressurized Reactors. Offsite Dose Calculation Manual Will Be Submitted by 840831.Future Submittals Will Address Listed Subjs

ML18018B728
Person / Time
Site:	Harris
Issue date:	07/30/1984
From:	Cutter A CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0452, RTR-NUREG-452 NLS-84-338, NUDOCS 8408060257
Download: ML18018B728 (5)

Text

1 REGULATOR~ .INFORMATION DISTRIBUTION 'TEM (RIDS),

IC ACCESSION NBR;8408060257 DOC ~ DATE: 84/07/30 NOTARIZED: NO DOCKET FACIL:50-400 BYNAME Shearon Harris Nuclear Power Plantq Unit 1~ Carolina 05000400 AUTH AUTHOR AFFILIATION CUTTER~A,B, Carolina Power,8, Light Co.

REC IP ~ NAME REC IPIE)T AFFILIATION DENTONpH ~ R>> Office of Nuclear Reactor Regulationr Director

SUBJECT:

Forwards marked up Tech Specs>based on Rev 4 to forl4estinghouse Pressurized Reactors." Offsite dose NUREG"0452'STS calculation manual will be submitted b'y 840831,Future submittals will address listed subjs.

DISTRIBUTION CODE'. B001S COPIES RECEIVED:LTR g ENCL g SIZE:

TITLE: Licensing Submittal: PSAR/FSAR Amdts 8 Related Correspondence NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR/DL/ADL NRR LB3 BC NRR LB3 LA BUCKLEYgB 01 1 1>>

INTERNAL: ADM-LFMB 1 ELD/HDS1 1 IE FILE 1 IE/DEPER/EPB 36 3 IE/DEPER/IRB 35 1 IE/DQAS IP/QA 121 1 NRR/DE/AEAB 1 NRR/DE/CEB 11 NRR/DE/EHEB 1 NRR/DE/EQB 13 2 s'

NRR/DE/GB 28 2 NRR/DE/MEB 18 1 NRR/DE/MTEB 17 1 NRR/DE/SAB 24 NRR/DE/SGEB 2S 1 NRR/DHFS/HFEB40 NRR/DHFS/LQB 32 1 NRR/DHFS/PSRB 1 NRR/DL/SSPB 1 NRR/DS I/AEB 26 1 NRR/DS I /ASB 1 NRR/DSI/CPB 10 1 NRR/DSI/CSB 09 1 NRR/DSI/ICSB 16 1 NRR/DS I/METB 12 1 NRR/DS I/PSB 19 1 NRR 22 1 NRR/0S I/RSB 23 1 b 04 1 RGN2 3 MI/MIB 1 EXTERNAL; ACRS 41 BNL(AMDTS ONLY) 1 DMB/DSS (AMDTS) F.EMA~REP DI V 39 1 LPDR , 03 NRC PDR 02 1 NSIC 05 NTIS 1 1>>

TOTAL NUMBER OF COPIES REQUIRED: LTTR 54 FNCL I

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CRK Carolina Power & Light Company SERIAL: NLS-84-338

.,JUL 3 0 1984, Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOo 1 DOCKET NO. 50-400 TECHNICAL SPECIFICATIONS

Dear Mr. Denton:

Carolina Power 6 Light Company (CPSL) hereby submits the "pen and ink" version of the Shearon Harris Nuclear Power Plant (SHNPP) Technical Specifications (Attachment 1). Five copies of this transmittal are being sent directly to Mr. Fred Anderson (NRC). This version of the SHNPP Technical Specifications is based on Revision 4 to NUREG-0452, "Standard Technical Specifications (STS) for Westinghouse Pressurized Reactors," along with guidance provided by the Standardization and Special Proj ects Branch. The Radiological Effluent Technical Specifications are incorporated into the Technical Specifications (within Attachment 1). The Environmental Technical Specifications are included as Appendix B to the Technical Specifications. The Offsite Dose Calculation Manual will be submitted by August 31, 1984. We will submit the Process Control Program six months prior to fuel load.

We have also provided an attachment to assist in the review of the SHNPP Technical Specifications (Attachment 2). Justification for changes to NUREG-0452 is provided along with a brief description of the source of specific documentation where a correlation between the value provided in a Specification and the FSAR or previous CP&L submittals can be made. In certain cases, this submittal provides information which supercedes the data currently in the FSAR. These items are also listed. The FSAR will be updated to reflect this new information. Finally, Attachment 2 provides a cross-reference to Final Safety Analysis Report (FSAR) and SER commitments related to Technical Specifications.

Information which is currently not available is indicated by a "(later)" or a blank. In instances where tentative information is available, by "(value)". We are proceeding to develop the missing information and plan it is indicated .

to submit it in the form of marked-up (revised) pages by November 1, 1984.

In addition to completion of the "later" items noted above, CPGL will provide future submittals to address the following sub) ects:

1. Westin house Owners'rou (WOG) Technical S ecification 0 timization Pro ram TOP We un erstan t at t e NRC review o t e TOP s u m tta for t e eactor rotection System is nearing completion. When the SER on this report is issued, CP&L will provide a submittal addressing the SER and providing appropriate changes to the SHNPP Technical Specifications. The WOG is also preparing a submittal using the TOP methodology for the A'DR 8408060257 840730 PDR ADOCK 05000400" g,'yetteville Street o P. O. 8ox 1551 a Raleigh, g. C. 2p502

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g Mr. Harold R. Dento Engineering Safety Featuxes Actuation System. The results of this effort will also be applicable to SHNPP and will be adopted when the NRC review is complete.

2. Slave Rela Testin The enclosed draft does not propose changes to the s ave re ay test ng recommended by NUREG-0452. Carolina Power 6 Light Company will perform a review of the slave relay testing capability of the SHNPP Solid State Plant Protection System and determine if testing of any slave relays, during power operation, could adversely quarterly affect plant safety or opexability. If CP&L concludes that quarterly testing should not be performed, a submittal listing the relays not tested and the bases for not testing will be provided to the NRC.

3. Im lementation Review of Technical S ecifications The implementation of t ese Tec n ca pec cat ons w un ergo an extensive review during the preparation of suxveillance procedures and during the use of these Technical Specifications during simulator training of operator license candidates. Where necessary to clarify a Specification and its applicability to the SHNPP design, additional changes will be provided to the NRC during the revi'ew process.

Based upon meetings with the NRC, the standard review schedule (Attachment 3) for SHNPP has been modified to accommodate an August 1984 submittal by CP6L.

We hope to have NRC's comments on the attached draft by December 1984 and will respond to them by January 15, 1985.

If you have any questions, please contact Mr. Gregg A. Sinders at (919) 836-8168 Yours ery tr A. B. Cutter Vic esident Nuclear Engineering 6 Licensing GAS/cfr (409GAS)

Attachments CC% Mr. F. Anderson (NRC-SSPB) Mr. Wells Eddleman Mr. B. C. Buckley (NRC) Mr. John D. Runkle Mr. G. F. Maxwell (NRC-SHNPP) Dr. Richard D. Wilson Mr. J. P. O'Reilly (NRC-RII) Mr. G. 0. Bright (ASLB)

Mr. Travis Payne (KUDZU) Dr. J. H. Carpenter (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Mr. J. L. Kelley (ASLB)

Chapel Hill Public Library Wake County Public Library