ML17346A813

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Forwards Updated Status of Inadequate Core Cooling Instrumentation Sys Implementation,In Response to NRC 841214 Request Re TMI Item II.F.2
ML17346A813
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 01/16/1985
From: Williams J
FLORIDA POWER & LIGHT CO.
To: Varga S
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM L-85-20, TAC-45176, TAC-45177, NUDOCS 8501230315
Download: ML17346A813 (8)


Text

REGULATORY I ORMATION DISTRIBUTION 'SYS (RIDS)

ACCESSION NBR 85012303 1 5 DOC ~ DATE o 85/0 1/1 6 NOTARIZED NO, DOCKE<T" FAGIL:50 250 Turkey Point Planti Unit 3E Florida Power and Light c 05000250 50-251 Turkey Point Planti Unit 4~ Florida Power and Light C 05000251 AUTHBNAME AUTHOR AFFILIATION WILLIAMS' ~ H~ Florida Power 5 Light Co, RECIP ~ NAME RECIPIENT AFFILIATION VARGAeS ~ AD Operating Reactors Branch 1

SUBJECT:

Forwards updated status of inadequate core coolipg instrumentation -sys implementationiin response to NRC" 841214 request re TMI Item II ~ F ~ 2 ~

DISTRIBUTION CODE: ADDED TITLE; OR Submittal COPIES RECEIVED ILTR iinadequate Cove. Cooling (Item I 'NCL" J II,F.2)

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GL 82 28 05000250 NOTES'L!07/19/72 05000251 OLD 04/14/73 RECIPIENT COPIES RECIP IENT'D COPIES ID CODE/NAME LTTR ENCLI CODE/NAME LTTR ENCL<

NRR ORB1 BC 1 1 NRR ORBi LA 1 1 ~

McDONALD,D 1 1 INTERNAL: ACRS 17 10 10 ADM/LFMB 1 0 NRR SHEA i J 01 1 1 NRR/DHFS/HFEB15'RR/DL/ORAB 1 1 NRR/DHFS/PSRB16 1 1 08 1 1 NRR/DL/ORBS 1 1 NRR/DSI DIR 09 1 1 NRR/DSI/CPB 10 3 3 /ICSB 1 1 NRR/DS I/RSB 13 1 1 G F 04 1 1 RGN2 07 1 1 EXTERNAL: LPDR 03 1 1 NRC PDR 02 1 1 NSIC 06 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 29

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/IIII A IL FLORIDA POWER & LIGHT COMPANY January 16, 1985 L-85-20 Office of Nuclear Reactor Regulation Attention: Mr. Steven A. Varga, Chief Operating Reactors Branch // I Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Varga:

Re: Turkey Point Units 3 & 4 Docket Nos. 50-250 & 50-25 I Inadequate Core Cooling Instrumentation (ICCI) System NUREG-0737, Item II.F.2 NRC TAC Nos. 45I76 & 45177 The attached information is submitted in response to your December l4, l984 letter which requested that FPL provide an updated status of the Turkey Point Units 3 & 4 ICCI implementation. This information supplements that included in our September 28, I 984 letter to you.

Should you or your staff have any questions regarding this information, please call USe Yours very truly, 6 %.PaW~Q.

Group Vice President Nuclear Energy JWW/TCG/kgn Attachment cc: J. P. O'Reilly,,Region II H. F. Reis, Esquire 8501'23031 5 PDR ADOCK 850116 05000250 PDR PEOPLE... SERVING PEOPLE

Turkey Point Units 3 end 4 Inadequate Core Cooling Instrumentation (ICCI) System Implementation The following updates or supplements the information included in FPL's September 20, l984 submittal (L-84-239) regarding ICCI Implementation.

Installation of the interconnecting cable from QSPDS to SAS will be made in conjunction with SPDS implementation scheduled to be completed during the upcoming refueling outages for Turkey Point Units 3 and 4.

2. The Ml cable/connector qualification test reports were received from Combustion Engineering on November 30, 1984 and are now being reviewed by FPL and Bechtel.
3. The following plant emergency operating and offnormal operating procedures have been revised to reflect the ICCS system installation. The revisions are consistent with the technical content of the NRC approved Westinghouse Owners Group Emergency Response Guidelines. Issue of the procedures and implementation has been delayed due to the large number of other procedures currently being revised by the plant staff. Implementation of these procedures is now expected to be completed by January 25, l985.

EOP 20000 (E-0) Immediate Actions and Diagnostics EOP 2000 I (E-I) Loss of Reactor Coolant EOP 20002 (E-2) Loss of Secondary Coolant EOP 20003 (E-3) Steam Generator Tube Rupture EOP 20004 Loss of Offsite Power EOP 20007 Loss of All A-C Power ONOP I 008.2 Excessive Reactor Coolant System Leakage ONOP I 008.3 Loss of Reactor Coolant Flow ONOP I 008.7 Reactor Coolant System Natural. Circulation ONOP I 008.8 Unit 3 - Natural Circulation Cooldown ONOP I 008.9 Unit 4- Natural Circulation Cooldown ONOP I 008. I 0 Response to Void in Reactor Vessel ONOP I 208. I Pressurizer Power Operated Relief System - (Reliefs and MOV's) - Malfunction

4. 's discussed in enclosure, item 7, (2) to FPL -letter L-84-239 dated September 20, 1984, the procedure walk-throughs to complete the task analysis portion of the ICCI System design will be done as part of the Task Analysis Upgrade Program (Detailed Control Room Design Review) and coordinated with the development and implementation of the procedures based on the approved Westinghouse Emergency Response Guidelines, which are scheduled to be completed by December 3I, l985. Specific task analyses

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using the interim EOP's and ONOP's referred to above will not be done.

Problems identified during their implementation will be resolved on a case by case basis. A systems function review and task analysis which included inadequate core cooling event sequences was performed as part of the Turkey Point Plant Units 3 and 4 Detailed Control Room Design Review and discussed in the Summary Report submitted to the NRC on November I, l983 (FPL letter L-83-547).

5. The hardware and software problems discussed during the audit are scheduled to be resolved by the end of the next refueling outage for each unit.
6. Proposed technical specifications for the ICCI System will be submitted by March l5, l985. They will be based on the guidance provided in Generic Letter 83-37, the additional guidance in the December l4, l984 NRC letter, and technical specifications for ICCI recently issued by the NRC.

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