ML17334B680: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
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'UTHOR AFFILIATION SCHOEPF,P.
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 PD3-3 PD COPIES RECIPIENT LTTR ENCL ID CODE/NAME 1 1 HICKMAN,J COPIES LTTR ENCL 1 1 R INTERNAL: PD RAB FIL NRR DE/EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN3 FILE 01 2'1 1 1 1 1 1 1 1 1 1 1 1 1 1 AEOD/S PD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB 1 1 1 1 1 1 1 1 1 1 1 1'1 1 D EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR 1 1 1 1 1 1 LITCO BRYCE,J H NOAC QUEENER,DS NUDOCS FULL TXT 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
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'se Even R , the following report is being submitted:
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 IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII IIIIIII NRC FORM 366 (5-92).S.NUCLEAR REGULATORY CQIIISS ION~LICENSEE EVENT REPORT (LER)H PROVED BY QIB NO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY'iiITH THI INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWAR COMHENI'S REGARDING BURDEN ESTIHATE TO THE 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)Donald C.Cook Nuclear Plant-Unit I DOCKET NtltBER (2)50-315 PAGE (3)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)MONTH 01 DAY YEAR 98 YEAR 98 SEQUENTIAL NUHBER REV!SION NUHBER 02 03 MONTH DAY YEAR 98 FACILITY NAME Donald C.Cook Nuclear Plant FACILITY NAHE DOCKET NUMBER 50-316 DOCKET NUMBER OPERATING M(XIE (9)POWER LEVEL (10)0 THIS REPORT IS SUBMITTED PURSUANT 20.2201(b) 20.2203(a)(1 20.2203(a)(2)(1) 20.2203(a)(3)(I) 20.2203(a)(3)(ii 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 73.71(b)73.71o OTHER TO THE REQUIREMENTS OF 10 CFR tia Check one or mor e)(11)20.2203(a (2 ii 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 50.36(c 1 50.36(c)(2) 50.73(a)(2)(I) x 50.73(a)(2)(ii)
RECIPIENT            COPIES              RECIPIENT             COPIES ID CODE/NAME         LTTR ENCL         ID CODE/NAME         LTTR ENCL PD3-3 PD                  1     1       HICKMAN,J                 1     1             R
LICENSEE CONTACT FOR THIS LER (12)50.73(a)(2 (vii 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x)(Specify in Abstract below and in Text, NRC Form 366A)NAHE Mr.Paul Schoepf-Safety Engineering Mechanical Systems Manager TELEPHONE NUMBER (Include Area Code)616/465-5901 Extension 2408 HIS REPORT (13)CQIPLETE OHE LINE FOR EACH CQIPONENT FAILURE DESCRIBED IN T CAUSE SYSTEM COMPOHENT MANUFACTURER REPORTABLE TO NPRDS CAUSE SYSTEH COMPOHENT MANUFACTURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14)X YES (if yes, complete EXPECTED SUBMISSION DATE).NO EXPECTED SUBili SS I OH DATE (15)MON 1'H DAY YEAR 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 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.
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:
In each case, initial testing indicated that low flow conditions existed in at least one localized portion of containment.
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
Investigation and evaluation of this event is ongoing.An update to this interim LER is to be issued by March 6, 1998.}}
 
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 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.}}

Revision as of 12:16, 22 October 2019

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
ML17334B680
Person / Time
Site: Cook American Electric Power icon.png
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.