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NO.DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME AUTHOR AFFILIATION WEBER,L.~.Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele SAMPSON,J.R. | ~ | ||
Indiana Michigan Power Co.(formerly Indiana 5-Michigan Ele RECIP.NAME RECIPIENT AFFILIATION | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) | ||
ACCESSION NBR:9809280272 DOC.DATE: 98/09/22 NOTARIZED: NO . DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH. NAME AUTHOR AFFILIATION WEBER,L. ~ .Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele SAMPSON,J.R. Indiana Michigan Power Co. (formerly Indiana 5 -Michigan Ele RECIP.NAME RECIPIENT AFFILIATION | |||
==SUBJECT:== | ==SUBJECT:== | ||
LER 98-039-00:on 980824,discovered that EOP procedural step conflicts with SBLOCA.Cause indeterminate. | LER 98-039-00:on 980824,discovered that EOP procedural step conflicts with SBLOCA.Cause indeterminate. Licensee will updated LER by 981116. | ||
Licensee will updated LER by 981116.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR i ENCL i SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT 1D CODE/NAME PD3-3 PD INTERNAL: AEOD S | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR i ENCL i SIZE: | ||
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22 Indiana Michigan Power Company Cook tadoar Pbrt One Cod<Rare | TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. | ||
NRC Form 366 | NOTES: | ||
OC 200004001, ANO TO THE PAPERWORK REDVCTION PROJECT DI 10010l).OFFICE OF MANAGEMENT ANO BUDGET.WASISNOTOIL OC 20NO | RECIPIENT COPIES RECIPIENT COPIES 1D CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG,J 1 1 INTERNAL: AEOD S 2 2 AEOD/SPD/RRAB 1. 1 E CE 1 ' | ||
POWER | 1 NRR/DE/ECGB 1 1 WWDE/EELB 1 NRR/DE/EMEB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOHB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 .1 NRR/DSSA/SPLB 1 1 RES/DET/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE, J H '1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 0 NOTE TO ALL "RIDS" RECIPIENTS: | ||
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22 | |||
The Westinghouse analysis assumed Sl pump flow would occur whenever the RCS pressure is less than 1350 psig.When instrument uncertainty associated with indicated RCS pressure is considered, the step to terminate Sl in the procedure could place the plant in an unanalyzed condition outside of the conditions assumed in the safety analysis whenever a small break LOCA occurs and the RCS pressure is less than 1350 psig.An ENS notification was made on August 24, 1998 at 1705 hours EDT in accordance with 10CFR50.72(b)(2)(i). | |||
This interim LER is therefore submitted under 10CFR50.73(a)(2)(ii) for an unanalyzed condition. | Indiana Michigan Power Company Cook tadoar Pbrt One Cod<Rare BridgnmMI49106 616 466 66o1 Z | ||
Westinghouse is currently evaluating the significance of the event.Based on the results of the evaluation an analysis is expected to provide recommendations on the adequacy of the EOPs and whether the condition reported represents an unanalyzed condition. | INOIANA NICHIGAN POWER September 22, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager: | ||
It is anticipated that an update to this LER will be submitted by November 16, 1998.NRC ORM 366'(4-95)}} | In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event d.'8-039-00 Sincerely, J. R. Sampson Site Vice President | ||
/mbd Attachment J. L. Caldwell, NRC R. P. Powers P. A. Barrett J. B. Kingseed R. Whale D. Hahn Records Center, INPO NRC Resident Inspector 980'rI280272 980922 050003i5 PDR ADQCK PDR | |||
P NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROYEO SY OMS NO. TI 004100 (4-95) EXPIRES OUJOJII ESTSIATEO SUROEN PER RESPONSE TO COMPLY WITH THIS MANDATORY LICENSEE EVENT REPORT (LER) ItKORMATlONCOLLECTCN REOUES'TI 50.0 HRS. REPORTED LESSONS LEARNED ARE NICORPCRATED PITO TNE VCENSINO PROCESS ANO FED SACK TO SIUSTRY FORWARD COMMENTS REGAROWO BURDEN ESTSAATE TO THE INFORMATION ANO RECORDS MANAGEMENT BRANCH (T4 PAL V.S. NUCLEAR REGIAATORY COMISSSICFL WASISNOTON. OC 200004001, ANO TO THE (See reverse for required number of PAPERWORK REDVCTION PROJECT DI 10010l). OFFICE OF MANAGEMENT ANO BUDGET. WASISNOTOIL OC 20NO digits/characters for each block) | |||
FACIUTYNAME (1) DOCKET NUMBER (2) PAGE (2) | |||
Cook Nuclear Plant Unit 1 50-315 1 of1 TITLE (0) | |||
Interim LER - Emergency Operating Procedural Step Conflicts with Small Break LOCA Analysis EVENT DATE (5) LER NUMBER (6) REPORT DATE P) OTHER FACILITIES INVOLVED(6) | |||
DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR A ILI NVM NUMBER NUMBER Cook Unit 2 50-316 A ILI NUM R 08 24 98 98 039 00 09 22 98 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I): (Check one or more) (11) | |||
MODE (9) 20.2201 (b) 20.2203(a)(2)(v) 50.73(a)(2)(i) 50.73(a)(2)(viii) | |||
POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x) | |||
LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(li) 20.2203(a)(4) 50.73(a)(2)()v) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) SI 50.73(a)(2)(v) SI NRC Form SQIA 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) | |||
LICENSEE CONTACT FOR THIS LER (12) | |||
TELEPHONE NUMBER(IGCSJdeAJes Code) | |||
Mr. Larry Weber, Operations Manager 616/465-5901 x2443 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) | |||
CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLETO CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED YES SUBMISSION DATE (15) 16 98 (If Yes, complete EXPECTED SUBMISSION DATE). | |||
Abstract (Umit to 1400 spaces, l,e., approximately 15 single-spaced typewritten lines) (16) | |||
On August 24, 1998 with Unit 1 and Unit 2 in Cold Shutdown, during a review of the current revision to the Emergency Operating Procedure (EOP), "Transfer to Cold Leg Recirculation," it was identified that the EOP contained a step that may not satisfy the assumptions made in the Westinghouse analysis for a small break loss of coolant accident (LOCA) at the point when Safety Injection (SI) pump flow would be delivered to the reactor core. The EOP procedure step requires the high head SI pumps to be turned off if Reactor Coolant System (RCS) pressure exceeds 1250 psig (1000 psig for adverse containment condition) with the pump minimum flow line returning Sl pump flow to the refueling water storage tank (RWST) isolated. The high head Sl pumps are turned off to prevent pump damage if they are not delivering the minimum required flow to prevent such damage. This would only leave the centrifugal charging pumps to deliver flow to the reactor in the event of a small break LOCA where the RCS remained at high pressures. The Westinghouse analysis assumed Sl pump flow would occur whenever the RCS pressure is less than 1350 psig. When instrument uncertainty associated with indicated RCS pressure is considered, the step to terminate Sl in the procedure could place the plant in an unanalyzed condition outside of the conditions assumed in the safety analysis whenever a small break LOCA occurs and the RCS pressure is less than 1350 psig. An ENS notification was made on August 24, 1998 at 1705 hours EDT in accordance with 10CFR50.72(b)(2)(i). This interim LER is therefore submitted under 10CFR50.73(a)(2)(ii) for an unanalyzed condition. | |||
Westinghouse is currently evaluating the significance of the event. Based on the results of the evaluation an analysis is expected to provide recommendations on the adequacy of the EOPs and whether the condition reported represents an unanalyzed condition. It is anticipated that an update to this LER will be submitted by November 16, 1998. | |||
NRC ORM 366'(4-95)}} | |||
Latest revision as of 11:02, 22 October 2019
| ML17335A243 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/22/1998 |
| From: | Sampson J, Weber L INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-98-039, LER-98-39, NUDOCS 9809280272 | |
| Download: ML17335A243 (4) | |
Text
CA.TEGORY '1 ~
~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9809280272 DOC.DATE: 98/09/22 NOTARIZED: NO . DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH. NAME AUTHOR AFFILIATION WEBER,L. ~ .Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele SAMPSON,J.R. Indiana Michigan Power Co. (formerly Indiana 5 -Michigan Ele RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 98-039-00:on 980824,discovered that EOP procedural step conflicts with SBLOCA.Cause indeterminate. Licensee will updated LER by 981116.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR i ENCL i SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES 1D CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG,J 1 1 INTERNAL: AEOD S 2 2 AEOD/SPD/RRAB 1. 1 E CE 1 '
1 NRR/DE/ECGB 1 1 WWDE/EELB 1 NRR/DE/EMEB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOHB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 .1 NRR/DSSA/SPLB 1 1 RES/DET/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE, J H '1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 0 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22
Indiana Michigan Power Company Cook tadoar Pbrt One Cod<Rare BridgnmMI49106 616 466 66o1 Z
INOIANA NICHIGAN POWER September 22, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager:
In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event d.'8-039-00 Sincerely, J. R. Sampson Site Vice President
/mbd Attachment J. L. Caldwell, NRC R. P. Powers P. A. Barrett J. B. Kingseed R. Whale D. Hahn Records Center, INPO NRC Resident Inspector 980'rI280272 980922 050003i5 PDR ADQCK PDR
P NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROYEO SY OMS NO. TI 004100 (4-95) EXPIRES OUJOJII ESTSIATEO SUROEN PER RESPONSE TO COMPLY WITH THIS MANDATORY LICENSEE EVENT REPORT (LER) ItKORMATlONCOLLECTCN REOUES'TI 50.0 HRS. REPORTED LESSONS LEARNED ARE NICORPCRATED PITO TNE VCENSINO PROCESS ANO FED SACK TO SIUSTRY FORWARD COMMENTS REGAROWO BURDEN ESTSAATE TO THE INFORMATION ANO RECORDS MANAGEMENT BRANCH (T4 PAL V.S. NUCLEAR REGIAATORY COMISSSICFL WASISNOTON. OC 200004001, ANO TO THE (See reverse for required number of PAPERWORK REDVCTION PROJECT DI 10010l). OFFICE OF MANAGEMENT ANO BUDGET. WASISNOTOIL OC 20NO digits/characters for each block)
FACIUTYNAME (1) DOCKET NUMBER (2) PAGE (2)
Cook Nuclear Plant Unit 1 50-315 1 of1 TITLE (0)
Interim LER - Emergency Operating Procedural Step Conflicts with Small Break LOCA Analysis EVENT DATE (5) LER NUMBER (6) REPORT DATE P) OTHER FACILITIES INVOLVED(6)
DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR A ILI NVM NUMBER NUMBER Cook Unit 2 50-316 A ILI NUM R 08 24 98 98 039 00 09 22 98 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I): (Check one or more) (11)
MODE (9) 20.2201 (b) 20.2203(a)(2)(v) 50.73(a)(2)(i) 50.73(a)(2)(viii)
POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x)
LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(li) 20.2203(a)(4) 50.73(a)(2)()v) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) SI 50.73(a)(2)(v) SI NRC Form SQIA 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
TELEPHONE NUMBER(IGCSJdeAJes Code)
Mr. Larry Weber, Operations Manager 616/465-5901 x2443 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLETO CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED YES SUBMISSION DATE (15) 16 98 (If Yes, complete EXPECTED SUBMISSION DATE).
Abstract (Umit to 1400 spaces, l,e., approximately 15 single-spaced typewritten lines) (16)
On August 24, 1998 with Unit 1 and Unit 2 in Cold Shutdown, during a review of the current revision to the Emergency Operating Procedure (EOP), "Transfer to Cold Leg Recirculation," it was identified that the EOP contained a step that may not satisfy the assumptions made in the Westinghouse analysis for a small break loss of coolant accident (LOCA) at the point when Safety Injection (SI) pump flow would be delivered to the reactor core. The EOP procedure step requires the high head SI pumps to be turned off if Reactor Coolant System (RCS) pressure exceeds 1250 psig (1000 psig for adverse containment condition) with the pump minimum flow line returning Sl pump flow to the refueling water storage tank (RWST) isolated. The high head Sl pumps are turned off to prevent pump damage if they are not delivering the minimum required flow to prevent such damage. This would only leave the centrifugal charging pumps to deliver flow to the reactor in the event of a small break LOCA where the RCS remained at high pressures. The Westinghouse analysis assumed Sl pump flow would occur whenever the RCS pressure is less than 1350 psig. When instrument uncertainty associated with indicated RCS pressure is considered, the step to terminate Sl in the procedure could place the plant in an unanalyzed condition outside of the conditions assumed in the safety analysis whenever a small break LOCA occurs and the RCS pressure is less than 1350 psig. An ENS notification was made on August 24, 1998 at 1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br /> EDT in accordance with 10CFR50.72(b)(2)(i). This interim LER is therefore submitted under 10CFR50.73(a)(2)(ii) for an unanalyzed condition.
Westinghouse is currently evaluating the significance of the event. Based on the results of the evaluation an analysis is expected to provide recommendations on the adequacy of the EOPs and whether the condition reported represents an unanalyzed condition. It is anticipated that an update to this LER will be submitted by November 16, 1998.
NRC ORM 366'(4-95)