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| issue date = 02/03/1998 | | issue date = 02/03/1998 | ||
| title = LER 98-001-00:on 980104,containment Air Recirculation Sys Flow Testing Results Indicate Condition Outside Design Basis.Investigation & Evaluation of Event Is Ongoing.Update to Interim LER Is to Be Issued on 980306.W/980203 Ltr | | title = LER 98-001-00:on 980104,containment Air Recirculation Sys Flow Testing Results Indicate Condition Outside Design Basis.Investigation & Evaluation of Event Is Ongoing.Update to Interim LER Is to Be Issued on 980306.W/980203 Ltr | ||
| author name = | | author name = Sampson J, Schoepf P | ||
| author affiliation = AMERICAN ELECTRIC POWER CO., INC. | | author affiliation = AMERICAN ELECTRIC POWER CO., INC. | ||
| addressee name = | | addressee name = | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:CATEGORY 1 (j REGULAT INFORMATION D1STRIBUTION SYSTEM (RIDS)i ACCESSION NBR:9802120287 DOC;DATE: 98/02/03 NOTARIZED: | {{#Wiki_filter:CATEGORY 1 (j REGULAT INFORMATION D1STRIBUTION SYSTEM (RIDS) i ACCESSION NBR:9802120287 DOC;DATE: 98/02/03 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear 'Power Plant, Unit 1, Indiana M 05000315 AUTH.NAMi'UTHORAFFILIATION SCHOEPF,P. American Electric Power Co., Inc. | ||
NO DOCKET FACIL:50-315 Donald C.Cook Nuclear'Power Plant, Unit 1, Indiana M 05000315 AUTH.NAMi' | SAMPSON,J.R. American Electric Power Co., Inc. | ||
American Electric Power Co., Inc.SAMPSON,J.R. | RECIP.NAME RECIPIENT AFFILIATION | ||
American Electric Power Co., Inc.RECIP.NAME RECIPIENT AFFILIATION | |||
==SUBJECT:== | ==SUBJECT:== | ||
LER 98-001-00:on 980104,containment air recirculation sys flow testing results indicate condition outside design basis.Investigation | LER 98-001-00:on 980104,containment air recirculation sys flow testing results indicate condition outside design basis. Investigation & evaluation of event is ongoing. Update to interim LER is to be issued 980306.W/980203 ltr. | ||
&evaluation of event is ongoing.Update to interim LER is to be issued 980306.W/980203 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR [ ENCL I SIZE: | ||
[ENCL I SIZE: T1TLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME | T1TLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. | ||
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 24 ENCL 24 American Electric Po~Cook Nuclear Plant One Cook Place Sridgman, Ml 49106 616 465 5901 AMER/CAN EEECTRIC POWER February 3, 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 | NOTES: | ||
98-001-00 Sincerely, John R.Sampson Site Vice President/tim Attachment c: A.B.Beach E.E.Fitzpatrick P.A.Barrett S.J.Brewer R.Whale D.Hahn Records Center, INPO NRC Resident Inspector)'it802i20287 980203 PDR ADOCK Q50003i5 8 PDR | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 HICKMAN,J 1 1 R INTERNAL: PD RAB 2 AEOD/S PD/RRAB 1 1 FIL 1 1 NRR/DE/ECGB 1 1 NRR DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DET/EIB '1 1 RGN3 FILE 01 1 1 D 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 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 24 ENCL 24 | |||
The testing was being performed as corrective action relative to an event reported in LER 316/97-009-00,"Blockage of Containment Air Recirculation Inlet Line Results in Condition Outside Design Basis." The testing was to confirm that required flows could be demonstrated for both containment air recirculation systems on both units.Initial results on the Unit 1 fan¹1 indicated that flow rates from various parts of containment were lower than values specified in the UFSAR.This condition was reported on January 5, 1998 at 0040 hours.Subsequent testing and notifications were made for the Unit 1 fan¹2, Unit 2 fan¹1, and Unit 2 fan¹2, on January 5, 1998 at 1900 hours, January 19, 1998 at 1310 hours, and January 20, 1998 at 1821 hours, respectively. | |||
In each case, initial testing indicated that low flow conditions existed in at least one localized portion of containment. | American Electric Po~ | ||
Investigation and evaluation of this event is ongoing.An update to this interim LER is to be issued by March 6, 1998.}} | Cook Nuclear Plant One Cook Place Sridgman, Ml 49106 616 465 5901 AMER/CAN EEECTRIC POWER February 3, 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 se Even R , the following report is being submitted: | |||
98-001-00 Sincerely, John R. Sampson Site Vice President | |||
/tim Attachment c: A. B. Beach E. E. Fitzpatrick P. A. Barrett S. J. Brewer R. Whale D. Hahn Records Center, INPO NRC Resident Inspector IIIIIII IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII | |||
) | |||
'it802i20287 980203 PDR ADOCK Q50003i5 8 PDR | |||
NRC FORM 366 .S. NUCLEAR REGULATORY CQIIISS ION PROVED BY QIB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY 'iiITH THI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWAR | |||
~ | |||
LICENSEE EVENT REPORT (LER) COMHENI'S REGARDING BURDEN ESTIHATE TO THE H | |||
INFORMATION AND RECORDS MANAGEMENT BRANCH (MNB 7714), U.S. NUCLEAR REGULATORY COMMISSIOH, WASHINGTON, DC 20555-0001, AND TO THE PAPERWOR REDUCT!ON PROJECT (3150-0104), OFFICE OF MANAGEHEHT AND BUDGET, WASHINGTON DC 20503. | |||
FACILITY NAME (1) DOCKET NtltBER (2) PAGE (3) | |||
Donald C. Cook Nuclear Plant -Unit I 50-315 1 OF 1 TITLE (4) Containment Air Recirculation System Flow Testing Results Indicate Condition Outside the Design Basis EVENT DATE (5) LER NUMBER 6) REPORT DATE (7 OTHER FACILITIES INVOLVED (8) | |||
SEQUENTIAL REV!SION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR Donald C. Cook Nuclear Plant 50-316 NUHBER NUHBER FACILITY NAHE DOCKET NUMBER 01 98 98 02 03 98 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR tia Check one or mor e) (11) | |||
M(XIE (9) 20.2201(b) 20.2203(a)(3)(I) 50.73(a)(2)(iii) 73.71(b) | |||
POWER 0 20.2203(a)(1 20.2203(a)(3)(ii 50.73(a)(2)(iv) 73.71o LEVEL (10) 20.2203(a)(2)(1) 20.2203(a)(4) 50.73(a)(2)(v) OTHER 20.2203(a (2 ii 50.36(c 1 50.73(a)(2 (vii (Specify in 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(viii)(A) Abstract below 20.2203(a)(2)(iv) 50.73(a)(2)(I) and in Text, 50.73(a)(2)(viii)(B) NRC Form 366A) 20.2203(a)(2)(v) x 50.73(a)(2)(ii) 50.73(a)(2)(x) | |||
LICENSEE CONTACT FOR THIS LER (12) | |||
NAHE TELEPHONE NUMBER (Include Area Code) | |||
Mr. Paul Schoepf - Safety Engineering Mechanical Systems Manager 616/465-5901 Extension 2408 CQIPLETE OHE LINE FOR EACH CQIPONENT FAILURE DESCRIBED IN T HIS REPORT (13) | |||
CAUSE SYSTEM REPORTABLE REPORTABLE COMPOHENT MANUFACTURER CAUSE SYSTEH COMPOHENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MON 1'H DAY YEAR X YES SUBiliSS I OH (if yes, complete EXPECTED SUBMISSION DATE). | |||
NO DATE (15) 03 06 98 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) | |||
This is an interim licensee event report (LER). This interim report is being submitted under 10 CFR 50.73(a)(2)(ii) as a condition outside the design basis. The report identifies that both Unit 1 and Unit 2 containment air recirculation systems did not perform as specified in the updated final safety analysis report (UFSAR). | |||
On January 4, 1998 containment air recirculation system testing was initiated. The testing was being performed as corrective action relative to an event reported in LER 316/97-009-00, "Blockage of Containment Air Recirculation Inlet Line Results in Condition Outside Design Basis." The testing was to confirm that required flows could be demonstrated for both containment air recirculation systems on both units. | |||
Initial results on the Unit 1 fan ¹1 indicated that flow rates from various parts of containment were lower than values specified in the UFSAR. This condition was reported on January 5, 1998 at 0040 hours. Subsequent testing and notifications were made for the Unit 1 fan ¹2, Unit 2 fan ¹1, and Unit 2 fan ¹2, on January 5, 1998 at 1900 hours, January 19, 1998 at 1310 hours, and January 20, 1998 at 1821 hours, respectively. In each case, initial testing indicated that low flow conditions existed in at least one localized portion of containment. | |||
Investigation and evaluation of this event is ongoing. An update to this interim LER is to be issued by March 6, 1998.}} |
Latest revision as of 00:36, 4 February 2020
ML17334B680 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 02/03/1998 |
From: | Sampson J, Schoepf P AMERICAN ELECTRIC POWER CO., INC. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
LER-98-001, LER-98-1, NUDOCS 9802120287 | |
Download: ML17334B680 (3) | |
Text
CATEGORY 1 (j REGULAT INFORMATION D1STRIBUTION SYSTEM (RIDS) i ACCESSION NBR:9802120287 DOC;DATE: 98/02/03 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear 'Power Plant, Unit 1, Indiana M 05000315 AUTH.NAMi'UTHORAFFILIATION SCHOEPF,P. American Electric Power Co., Inc.
SAMPSON,J.R. American Electric Power Co., Inc.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 98-001-00:on 980104,containment air recirculation sys flow testing results indicate condition outside design basis. Investigation & evaluation of event is ongoing. Update to interim LER is to be issued 980306.W/980203 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR [ ENCL I SIZE:
T1TLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD 1 1 HICKMAN,J 1 1 R INTERNAL: PD RAB 2 AEOD/S PD/RRAB 1 1 FIL 1 1 NRR/DE/ECGB 1 1 NRR DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DET/EIB '1 1 RGN3 FILE 01 1 1 D 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 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 24 ENCL 24
American Electric Po~
Cook Nuclear Plant One Cook Place Sridgman, Ml 49106 616 465 5901 AMER/CAN EEECTRIC POWER February 3, 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 se Even R , the following report is being submitted:
98-001-00 Sincerely, John R. Sampson Site Vice President
/tim Attachment c: A. B. Beach E. E. Fitzpatrick P. A. Barrett S. J. Brewer R. Whale D. Hahn Records Center, INPO NRC Resident Inspector IIIIIII IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII
)
'it802i20287 980203 PDR ADOCK Q50003i5 8 PDR
NRC FORM 366 .S. NUCLEAR REGULATORY CQIIISS ION PROVED BY QIB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY 'iiITH THI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWAR
~
LICENSEE EVENT REPORT (LER) COMHENI'S REGARDING BURDEN ESTIHATE TO THE H
INFORMATION AND RECORDS MANAGEMENT BRANCH (MNB 7714), U.S. NUCLEAR REGULATORY COMMISSIOH, WASHINGTON, DC 20555-0001, AND TO THE PAPERWOR REDUCT!ON PROJECT (3150-0104), OFFICE OF MANAGEHEHT AND BUDGET, WASHINGTON DC 20503.
FACILITY NAME (1) DOCKET NtltBER (2) PAGE (3)
Donald C. Cook Nuclear Plant -Unit I 50-315 1 OF 1 TITLE (4) Containment Air Recirculation System Flow Testing Results Indicate Condition Outside the Design Basis EVENT DATE (5) LER NUMBER 6) REPORT DATE (7 OTHER FACILITIES INVOLVED (8)
SEQUENTIAL REV!SION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR Donald C. Cook Nuclear Plant 50-316 NUHBER NUHBER FACILITY NAHE DOCKET NUMBER 01 98 98 02 03 98 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR tia Check one or mor e) (11)
M(XIE (9) 20.2201(b) 20.2203(a)(3)(I) 50.73(a)(2)(iii) 73.71(b)
POWER 0 20.2203(a)(1 20.2203(a)(3)(ii 50.73(a)(2)(iv) 73.71o LEVEL (10) 20.2203(a)(2)(1) 20.2203(a)(4) 50.73(a)(2)(v) OTHER 20.2203(a (2 ii 50.36(c 1 50.73(a)(2 (vii (Specify in 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(viii)(A) Abstract below 20.2203(a)(2)(iv) 50.73(a)(2)(I) and in Text, 50.73(a)(2)(viii)(B) NRC Form 366A) 20.2203(a)(2)(v) x 50.73(a)(2)(ii) 50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER (12)
NAHE TELEPHONE NUMBER (Include Area Code)
Mr. Paul Schoepf - Safety Engineering Mechanical Systems Manager 616/465-5901 Extension 2408 CQIPLETE OHE LINE FOR EACH CQIPONENT FAILURE DESCRIBED IN T HIS REPORT (13)
CAUSE SYSTEM REPORTABLE REPORTABLE COMPOHENT MANUFACTURER CAUSE SYSTEH COMPOHENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MON 1'H DAY YEAR X YES SUBiliSS I OH (if yes, complete EXPECTED SUBMISSION DATE).
NO DATE (15) 03 06 98 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
This is an interim licensee event report (LER). This interim report is being submitted under 10 CFR 50.73(a)(2)(ii) as a condition outside the design basis. The report identifies that both Unit 1 and Unit 2 containment air recirculation systems did not perform as specified in the updated final safety analysis report (UFSAR).
On January 4, 1998 containment air recirculation system testing was initiated. The testing was being performed as corrective action relative to an event reported in LER 316/97-009-00, "Blockage of Containment Air Recirculation Inlet Line Results in Condition Outside Design Basis." The testing was to confirm that required flows could be demonstrated for both containment air recirculation systems on both units.
Initial results on the Unit 1 fan ¹1 indicated that flow rates from various parts of containment were lower than values specified in the UFSAR. This condition was reported on January 5, 1998 at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Subsequent testing and notifications were made for the Unit 1 fan ¹2, Unit 2 fan ¹1, and Unit 2 fan ¹2, on January 5, 1998 at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, January 19, 1998 at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br />, and January 20, 1998 at 1821 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.928905e-4 months <br />, respectively. In each case, initial testing indicated that low flow conditions existed in at least one localized portion of containment.
Investigation and evaluation of this event is ongoing. An update to this interim LER is to be issued by March 6, 1998.