ML18018B728: Difference between revisions

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| issue date = 07/30/1984
| issue date = 07/30/1984
| title = 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
| title = 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
| author name = CUTTER A B
| author name = Cutter A
| author affiliation = CAROLINA POWER & LIGHT CO.
| author affiliation = CAROLINA POWER & LIGHT CO.
| addressee name = DENTON H R
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000400
| docket = 05000400

Revision as of 05:26, 18 June 2019

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 Duke Energy icon.png
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 FACIL:50-400 Shearon Harris Nuclear Power Plantq Unit 1~Carolina AUTH BYNAME 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 NUREG"0452'STS forl4estinghouse Pressurized Reactors." Offsite dose 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 DOCKET 05000400 RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA INTERNAL: ADM-LFMB IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 2S NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/DS I/METB 12 NRR 22 b 04 MI/MIB , EXTERNAL;ACRS 41 DMB/DSS (AMDTS)LPDR , 03 NSIC 05 COPIES LTTR ENCL 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME NRR LB3 BC BUCKLEYgB 01 ELD/HDS1 IE/DEPER/EPB 36 IE/DQAS IP/QA 121 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DS I/PSB 19 NRR/0S I/RSB 23 RGN2 BNL(AMDTS ONLY)F.EMA~REP DI V 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1 1>>1 3 1 2 1 s'1 1 1 1 1 1 3 1 1 1 1 1>>TOTAL NUMBER OF COPIES REQUIRED: LTTR 54 FNCL I c'I ly h II II I, I CRK Carolina Power&Light Company.,JUL 3 0 1984, SERIAL: NLS-84-338 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, it is indicated.by"(value)".

We are proceeding to develop the missing information and plan to submit it in the form of marked-up (revised)pages by November 1, 1984.1.Westin house Owners'rou (WOG)Technical S ecification 0 timization T s m tta f Pro ram TOP We un erstan t at t e NRC review o t e OP u or 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 In addition to completion of the"later" items noted above, CPGL will provide future submittals to address the following sub)ects: 8408060257 840730 PDR ADOCK 05000400" A'DR g,'yetteville Street o P.O.8ox 1551 a Raleigh, g.C.2p502 Ny t'1 QA~li ff jl~I 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 quarterly testing of any slave relays, during power operation, could adversely 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 GAS/cfr (409GAS)Attachments A.B.Cutter-Vic esident Nuclear Engineering 6 Licensing CC%Mr.F.Anderson (NRC-SSPB)

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 Mr.John D.Runkle Dr.Richard D.Wilson Mr.G.0.Bright (ASLB)Dr.J.H.Carpenter (ASLB)Mr.J.L.Kelley (ASLB)