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| #REDIRECT [[05000245/LER-1996-054-01]] | | {{Adams |
| | | number = ML20134J785 |
| | | issue date = 11/13/1996 |
| | | title = :on 961030,high Range Stack Gas Monitor Failed & Declared Inoperable.Due to Intermittent Nature of Failure. Cause of Event Will Be Provided in Supplemental Rept.Cause of Intermittent Failures Will Be Determined |
| | | author name = Hinnenkamp P, Walpole R |
| | | author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO. |
| | | addressee name = |
| | | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | | docket = 05000245 |
| | | license number = |
| | | contact person = |
| | | document report number = B16005, LER-96-054, LER-96-54, NUDOCS 9611180062 |
| | | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT |
| | | page count = 4 |
| | }} |
| | {{LER |
| | | Title = :on 961030,high Range Stack Gas Monitor Failed & Declared Inoperable.Due to Intermittent Nature of Failure. Cause of Event Will Be Provided in Supplemental Rept.Cause of Intermittent Failures Will Be Determined |
| | | Plant = |
| | | Reporting criterion = 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(viii), 10 CFR 50.73(a)(2)(ii), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(iv), 10 CFR 50.73(a)(2)(v), 10 CFR 50.73(a)(2)(vii) |
| | | Power level = |
| | | Mode = |
| | | Docket = 05000245 |
| | | LER year = 1996 |
| | | LER number = 54 |
| | | LER revision = 0 |
| | | Event date = |
| | | Report date = |
| | | ENS = |
| | | abstract = |
| | }} |
| | |
| | =text= |
| | {{#Wiki_filter:, |
| | . ~..... -. |
| | D Northeast men, omm. nope r rry na. waierrora, cr l |
| | g$, Utilities Systent p.o.801128 l |
| | Waterford, CT 06385-0128 (203) 447-1791 November 13,1996 Docket No. 50-245 B16005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 l |
| | This letter forwards Licensee Event Report (LER) 96-054-00, documenting an event that occurred at Millstone Nuclear Power Station, Unit No.1 on October 30,1996. This LER is submitted as a Special Report, pursuant to the Millstone Unit No.1 Technical Specifications. |
| | The following are Northeast Nuclear Energy Company's commitments made within this letter. |
| | ' All other statements made within this letter are for information only. |
| | B16005-1 The cause of the intermittent failures will be determined and it is expected that the l |
| | High Range Stack Noble Gas Monitor will be returned to service prior to i |
| | November 30,1996. |
| | B16005-2 Supplemental report will be submitted prior to December 15,- 1996, with cause of the intermittent problems. |
| | Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY j |
| | f-L P. D. Hinnenkamp V |
| | Director, Unit Operations 9611100062 96 1 3 l |
| | PDR ADOCK 05000245 1 |
| | j. |
| | S PDR i |
| | Attachment: LER 96-054-00 i |
| | Y cc: |
| | H. J. Miller, Region 1 Administrator T. A. Eastick, Senior Resident Inspector, Millstone Unit No. I J. W. Andersen, NRC Project Manager, Millstone Unit No. I osa422., nov. i.,s l |
| | I |
| | |
| | [ |
| | NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB N0. 31504)104 14 95) |
| | EXPlRES 04/30/98 fNFO ATION COLLE T ON R QUES 50 0 HR$ |
| | E RTED L S n'a"'?o^"AoM?Ri "^4%#Po 'EaJn'N"T's" Jo"aT$ ^3fa a |
| | LICENSEE EVENT REPORT (LER) 15p,"4"U'f ucW;a"R4'agl<gg,"us;#o'"a',,gfg"& |
| | o |
| | !?inWhaMM?afi"Mif. E'ES3"ol35;&'"" |
| | (See reverse for required number of digits / characters for each block) |
| | FACluTY NAME nl DOCKET NUMBER (2) |
| | PAGE (3) |
| | Millstone Nuclear Power Station Unit 1 05000245 1 of 3 TITLE 14) |
| | High Range Stack Noble Gas Monitor inoperable EVENT DATE (5) |
| | LER NUMBER (6) |
| | REPORT DATE (7) |
| | OTHER FACILITIES INVOLVED (8) |
| | MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACluTY NAME DOCKET NUMBER NUMBER 10 30 96 96 054 00 11 13 96 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR B: (Check one or more) (11) |
| | MODE (9) |
| | N 20.2201(b) 20.2203(a)(2)(v) 50.73(a)(2)(i) 50.73(a)(2)(viii) |
| | POWER 20.2203(a)(11 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x) |
| | LEVEL (10) 000 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) |
| | X OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v) specify in Abstract below I |
| | A 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) |
| | SpTcYaNeElo7t 66A LICENSEE CONTACT FOR THIS LER (12) |
| | NAME TELEPHONE NUMBER linclude Area Codel Robert W. Walpole, MP1 Nuclear Licensing Manager (860)440-2191 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | |
| | ==CAUSE== |
| | SYSTEM COMPONENT MANUFACTURER REPORTABLE |
| | |
| | ==CAUSE== |
| | SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDs TO NPRDS l |
| | l SUPPLEMENTAL REPORT EXPECTED (14) |
| | EXPECTED MONTH DAY YEAR j |
| | SUBMISSION f |
| | YES NO 12 15 96 l |
| | (if yes, complete EXPECTED SUBMISSION DATE). |
| | l ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) i l |
| | On October 30,1996 at 0525 hours, with the plant shutdown and the reactor in the COLD SHUTDOWN condition, the High Range Stack Noble Gas Monitor failed and was declared inoperable. Due to the intermittent nature of the failure, subsequent troubleshooting could not determine a definitive cause of the problem; therefore, the monitor remains inoperable with the alternate pre-planned method established in accordance with Technical Specification 3.8.D.7 to monitor stack effluent releases. An extensive troubleshooting effort has been initiated with resources from Millstone Unit Nos.1 and 3, as well as the services of the vendor to determine the cause of the intermittent failures and return the High Range Stack Noble Gas Monitor to service. |
| | This event is reportable pursuant to Millstone Unit No.1 Technical Specification 3.8.D.7, which requires the submission of a Special Report to NRC, within 14 days of the event, when the High Range Stack Noble Gas Monitor cannot be made operable within seven days. |
| | NRC FORM 366 (4-95) |
| | |
| | 4', |
| | fiRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95) |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY NAME (1) |
| | DOCKET NUMBER (2) |
| | LER NUMBER (6) |
| | PAGE (3) |
| | YEAR SEQUENTIAL REVISION Millstone Nuclear Power Station Unit 1 05000245 NUMBER NUMBER 2 of 3 96 054 00 TEXT lif more space is required, use additional copies of NRC Form 366A) (17) 1. |
| | Descriotion of Event On October 30,1996 at 0525 hours, with the plant shutdown and the reactor in the COLD SHUTDOWN condition, the High Range Stack Noble Gas Monitor failed and was declared inoperable. Troubleshooting revealed that several circuit boards were suspect and replaced, which allowed the monitor to operate. Since it was not known whether the suspect boards failed on their own or due to another problem that still existed within the monitor, the monitor was left as inoperable. Additionally, recent intermittent problems with the monitor resulted in the conclusion that continued troubleshooting, which consisted of component replacement and subsequent monitoring for intermittent problems, was necessary to obtain reasonable assurance that the monitor would function properly when returned to service. Subsequently, the monitor failed again due to an unknown cause. |
| | At this point, it was determined that since a definitive problem could not be found, the monitor would not be returned to service in a timely manner. Due to the history of intermittent problems that have surfaced with this instrurnent over the past several months and the failure of troubleshooting efforts to identify the root cause, it was deemed necessary to develop a plan to conduct extensive troubleshooting and system walkdowns to validate proper grounding, noise protection, and compliance with recommended installation instructions. Alternate pre-planned actions have been initiated and will remain in effect in accordance with Technical Specification 3.8.D.7. |
| | II. |
| | |
| | ==Cause of Event== |
| | The cause of the event will be provided in a supplemental report. |
| | Ill. Analvsis of Event Per the Millstone Unit no.1 Updated Final Safety Analysis Report (UFSAR), the process and effluent monitoring system provides a means for compliance with 10CFR20,10CFR50 Appendix A GDC 60,63, and 64, and Regulatory Guides 1.21,1.97,4.15, and 8.8. The High Range Stack Noble Gas Monitor measures the gross gamma activity of noble gases exiting the Millstone Unit No.1 Main Stack to provide information to the operator for assessing plant conditions and classification of events, during and following an accident. |
| | This event is reportable pursuant to Millstone Unit No.1 Technical Specification 3.8.D.7, which requires the submission of a Special Report to NRC, within 14 days of the event, when the High Range Stack Noble Gas Monitor cannot be made operable within seven days. |
| | The High Range Stack Noble Gas Monitor is required to be operable at all times. The bases of the Technical Specifications delineates that, since the Millstone Unit No.1 stack represents the final release point for potential accident level releases from all three Millstone units, the applicability has been defined as at all times rather than relating it solely to Millstone Unit No. 1 operating modes. There are no safety consequences since the Millstone Unit No.1 Main Stack Noble Gas Activity Monitor remains operable as the initial alternate, pre-planned method to monitor effluent releases, in the event of an accident involving a release through the Main Stack, additional monitoring methods are available as described in Emergency Plan Operating Procedures. |
| | . ~ _. -.. |
| | e 4 |
| | ERC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 4 |
| | (4 95) |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY NAME (1) |
| | DOCKET NUMBER (2) |
| | LER NUMBER (6) |
| | PAGE (3) |
| | YEAR SEQUENTIAL REVISION Millstone Nuclear Power Station Unit 1 05000245 NUMBER NUMBER 3 of 3 96 054 00 1 |
| | 3 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| | J |
| | |
| | ==IV. Corrective Action== |
| | The cause of the intermittent failures will be determined and it is expected that the High Range Stack Noble i |
| | Gas Monitor will be returned to service prior to November 30,1996. |
| | Supplemental report will be submitted prior to December 15,1996, with cause of the intermittent problems. |
| | j V. |
| | Additional InformatiDD |
| | |
| | ==Similar Events== |
| | LER 96-044-01, dated: 7/29/96, "High Range Stack Noble Gas Monitor Inoperable Due to inadequate Calibration" LER 95-015-00, dated 8/21/95, " Stack High Range Noble Gas Radiation Monitor inoperable" Manufacturer Data None. |
| | }} |
| | |
| | {{LER-Nav}} |
text
,
. ~..... -.
D Northeast men, omm. nope r rry na. waierrora, cr l
g$, Utilities Systent p.o.801128 l
Waterford, CT 06385-0128 (203) 447-1791 November 13,1996 Docket No. 50-245 B16005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 l
This letter forwards Licensee Event Report (LER) 96-054-00, documenting an event that occurred at Millstone Nuclear Power Station, Unit No.1 on October 30,1996. This LER is submitted as a Special Report, pursuant to the Millstone Unit No.1 Technical Specifications.
The following are Northeast Nuclear Energy Company's commitments made within this letter.
' All other statements made within this letter are for information only.
B16005-1 The cause of the intermittent failures will be determined and it is expected that the l
High Range Stack Noble Gas Monitor will be returned to service prior to i
November 30,1996.
B16005-2 Supplemental report will be submitted prior to December 15,- 1996, with cause of the intermittent problems.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY j
f-L P. D. Hinnenkamp V
Director, Unit Operations 9611100062 96 1 3 l
PDR ADOCK 05000245 1
j.
S PDR i
Attachment: LER 96-054-00 i
Y cc:
H. J. Miller, Region 1 Administrator T. A. Eastick, Senior Resident Inspector, Millstone Unit No. I J. W. Andersen, NRC Project Manager, Millstone Unit No. I osa422., nov. i.,s l
I
[
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB N0. 31504)104 14 95)
EXPlRES 04/30/98 fNFO ATION COLLE T ON R QUES 50 0 HR$
E RTED L S n'a"'?o^"AoM?Ri "^4%#Po 'EaJn'N"T's" Jo"aT$ ^3fa a
LICENSEE EVENT REPORT (LER) 15p,"4"U'f ucW;a"R4'agl<gg,"us;#o'"a',,gfg"&
o
!?inWhaMM?afi"Mif. E'ES3"ol35;&'""
(See reverse for required number of digits / characters for each block)
FACluTY NAME nl DOCKET NUMBER (2)
PAGE (3)
Millstone Nuclear Power Station Unit 1 05000245 1 of 3 TITLE 14)
High Range Stack Noble Gas Monitor inoperable EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACluTY NAME DOCKET NUMBER NUMBER 10 30 96 96 054 00 11 13 96 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR B: (Check one or more) (11)
MODE (9)
N 20.2201(b) 20.2203(a)(2)(v) 50.73(a)(2)(i) 50.73(a)(2)(viii)
POWER 20.2203(a)(11 20.2203(a)(3)(i) 50.73(a)(2)(ii) 50.73(a)(2)(x)
LEVEL (10) 000 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv)
X OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50.73(a)(2)(v) specify in Abstract below I
A 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii)
SpTcYaNeElo7t 66A LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER linclude Area Codel Robert W. Walpole, MP1 Nuclear Licensing Manager (860)440-2191 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDs TO NPRDS l
l SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR j
SUBMISSION f
YES NO 12 15 96 l
(if yes, complete EXPECTED SUBMISSION DATE).
l ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) i l
On October 30,1996 at 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br />, with the plant shutdown and the reactor in the COLD SHUTDOWN condition, the High Range Stack Noble Gas Monitor failed and was declared inoperable. Due to the intermittent nature of the failure, subsequent troubleshooting could not determine a definitive cause of the problem; therefore, the monitor remains inoperable with the alternate pre-planned method established in accordance with Technical Specification 3.8.D.7 to monitor stack effluent releases. An extensive troubleshooting effort has been initiated with resources from Millstone Unit Nos.1 and 3, as well as the services of the vendor to determine the cause of the intermittent failures and return the High Range Stack Noble Gas Monitor to service.
This event is reportable pursuant to Millstone Unit No.1 Technical Specification 3.8.D.7, which requires the submission of a Special Report to NRC, within 14 days of the event, when the High Range Stack Noble Gas Monitor cannot be made operable within seven days.
NRC FORM 366 (4-95)
4',
fiRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION Millstone Nuclear Power Station Unit 1 05000245 NUMBER NUMBER 2 of 3 96 054 00 TEXT lif more space is required, use additional copies of NRC Form 366A) (17) 1.
Descriotion of Event On October 30,1996 at 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br />, with the plant shutdown and the reactor in the COLD SHUTDOWN condition, the High Range Stack Noble Gas Monitor failed and was declared inoperable. Troubleshooting revealed that several circuit boards were suspect and replaced, which allowed the monitor to operate. Since it was not known whether the suspect boards failed on their own or due to another problem that still existed within the monitor, the monitor was left as inoperable. Additionally, recent intermittent problems with the monitor resulted in the conclusion that continued troubleshooting, which consisted of component replacement and subsequent monitoring for intermittent problems, was necessary to obtain reasonable assurance that the monitor would function properly when returned to service. Subsequently, the monitor failed again due to an unknown cause.
At this point, it was determined that since a definitive problem could not be found, the monitor would not be returned to service in a timely manner. Due to the history of intermittent problems that have surfaced with this instrurnent over the past several months and the failure of troubleshooting efforts to identify the root cause, it was deemed necessary to develop a plan to conduct extensive troubleshooting and system walkdowns to validate proper grounding, noise protection, and compliance with recommended installation instructions. Alternate pre-planned actions have been initiated and will remain in effect in accordance with Technical Specification 3.8.D.7.
II.
Cause of Event
The cause of the event will be provided in a supplemental report.
Ill. Analvsis of Event Per the Millstone Unit no.1 Updated Final Safety Analysis Report (UFSAR), the process and effluent monitoring system provides a means for compliance with 10CFR20,10CFR50 Appendix A GDC 60,63, and 64, and Regulatory Guides 1.21,1.97,4.15, and 8.8. The High Range Stack Noble Gas Monitor measures the gross gamma activity of noble gases exiting the Millstone Unit No.1 Main Stack to provide information to the operator for assessing plant conditions and classification of events, during and following an accident.
This event is reportable pursuant to Millstone Unit No.1 Technical Specification 3.8.D.7, which requires the submission of a Special Report to NRC, within 14 days of the event, when the High Range Stack Noble Gas Monitor cannot be made operable within seven days.
The High Range Stack Noble Gas Monitor is required to be operable at all times. The bases of the Technical Specifications delineates that, since the Millstone Unit No.1 stack represents the final release point for potential accident level releases from all three Millstone units, the applicability has been defined as at all times rather than relating it solely to Millstone Unit No. 1 operating modes. There are no safety consequences since the Millstone Unit No.1 Main Stack Noble Gas Activity Monitor remains operable as the initial alternate, pre-planned method to monitor effluent releases, in the event of an accident involving a release through the Main Stack, additional monitoring methods are available as described in Emergency Plan Operating Procedures.
. ~ _. -..
e 4
ERC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 4
(4 95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION Millstone Nuclear Power Station Unit 1 05000245 NUMBER NUMBER 3 of 3 96 054 00 1
3 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
J
IV. Corrective Action
The cause of the intermittent failures will be determined and it is expected that the High Range Stack Noble i
Gas Monitor will be returned to service prior to November 30,1996.
Supplemental report will be submitted prior to December 15,1996, with cause of the intermittent problems.
j V.
Additional InformatiDD
Similar Events
LER 96-044-01, dated: 7/29/96, "High Range Stack Noble Gas Monitor Inoperable Due to inadequate Calibration" LER 95-015-00, dated 8/21/95, " Stack High Range Noble Gas Radiation Monitor inoperable" Manufacturer Data None.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000336/LER-1996-001, :on 960625,discovered Reactor Coolant Sys Heatup Rate Exceeded Tech Spec.Caused by Design & Procedural Weaknesses Re Plant Heatup Controls.Revised Plant Operating Procedures & Heatup/Cooldown Computer Program |
- on 960625,discovered Reactor Coolant Sys Heatup Rate Exceeded Tech Spec.Caused by Design & Procedural Weaknesses Re Plant Heatup Controls.Revised Plant Operating Procedures & Heatup/Cooldown Computer Program
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000423/LER-1996-001-02, :on 960120,supplementary Leak Collection & Release Sys Declared Inoperable Due to Equipment Failure of Door Latch.Door Repaired & Plant Returned to 100% Power |
- on 960120,supplementary Leak Collection & Release Sys Declared Inoperable Due to Equipment Failure of Door Latch.Door Repaired & Plant Returned to 100% Power
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000336/LER-1996-002, :on 960108,determined That Ice Plug in Common Line Resulted in Inability to Backwash Svc Water Strainers. Caused by Mod to Backwash Line Piping.Ice Plug Removed, Restoring Ability to Backwash |
- on 960108,determined That Ice Plug in Common Line Resulted in Inability to Backwash Svc Water Strainers. Caused by Mod to Backwash Line Piping.Ice Plug Removed, Restoring Ability to Backwash
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | | 05000423/LER-1996-002-02, :on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Identified. Caused by Inadequate Procedure.Procedures Revised |
- on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Identified. Caused by Inadequate Procedure.Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) | | 05000423/LER-1996-002, :on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Occurred Due to Procedure Inadequacy.Changes Will Be Made to Technical Requirements Manual |
- on 960310,inadequate Surveillance for Determining Shutdown Margin When Unisolating Rcl Occurred Due to Procedure Inadequacy.Changes Will Be Made to Technical Requirements Manual
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000245/LER-1996-003, :on 960111,discovered Existing Anchorage of EDG Day Tank Not Seismically Adequate.Caused by Original Design Deficiency.Anchorage of EDG Tank Will Be Graded to Meet Design Basis of Seismic Load Requirements |
- on 960111,discovered Existing Anchorage of EDG Day Tank Not Seismically Adequate.Caused by Original Design Deficiency.Anchorage of EDG Tank Will Be Graded to Meet Design Basis of Seismic Load Requirements
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(e)(2)(i) 10 CFR 50.73(e)(2)(viii) | | 05000336/LER-1996-003-01, :on 960205,failed to Recognize Requirement to Enter TS LCO 3.0.3 Following Discovery of Ice Blockage. Caused by Inadequate Problem Identification Methods.Design Basis Summary Documents Have Been Prepared Re TS Safety Sys |
- on 960205,failed to Recognize Requirement to Enter TS LCO 3.0.3 Following Discovery of Ice Blockage. Caused by Inadequate Problem Identification Methods.Design Basis Summary Documents Have Been Prepared Re TS Safety Sys
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000245/LER-1996-003-02, Forwards LER 96-003-02 Which Documents an Event That Occurred at Mnps,Unit 1 on 960111,per 10CFR50.73(a)(2)(i) & 10CFR50.73(a)(2)(ii).Commitments Made in Ltr,Submitted | Forwards LER 96-003-02 Which Documents an Event That Occurred at Mnps,Unit 1 on 960111,per 10CFR50.73(a)(2)(i) & 10CFR50.73(a)(2)(ii).Commitments Made in Ltr,Submitted | 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000423/LER-1996-003-01, :on 960312,temporary I-Beams Located Overhead of Recirculation Spray Sys HXs Discovered.Caused by Inadequate Work Control.Work Control Procedures Revised |
- on 960312,temporary I-Beams Located Overhead of Recirculation Spray Sys HXs Discovered.Caused by Inadequate Work Control.Work Control Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000423/LER-1996-004-01, :on 960319,determined That Auxiliary Feedwater Isolation Valves Were in Noncompliance W/Ts.Caused by Misinterpretation of Ts.Revised Operating Procedure to Preclude cross-connected Sys Alignment |
- on 960319,determined That Auxiliary Feedwater Isolation Valves Were in Noncompliance W/Ts.Caused by Misinterpretation of Ts.Revised Operating Procedure to Preclude cross-connected Sys Alignment
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) | | 05000336/LER-1996-004, :on 960131,svc Water Strainer Backwash Sys Susceptibility to Freezing Following Loss of Intake Structure non-vital Heating Occurred.Caused by Inadequate Original Design.Design Change Implemented |
- on 960131,svc Water Strainer Backwash Sys Susceptibility to Freezing Following Loss of Intake Structure non-vital Heating Occurred.Caused by Inadequate Original Design.Design Change Implemented
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000423/LER-1996-004-02, :on 960316,auxiliary Feedwater Isolation Valves Noncompliance W/Ts Occurred.Caused by Misinterpretation of Ts.Event Reviewed W/Station Personnel to Caution Others on TS Surveillance Requirements |
- on 960316,auxiliary Feedwater Isolation Valves Noncompliance W/Ts Occurred.Caused by Misinterpretation of Ts.Event Reviewed W/Station Personnel to Caution Others on TS Surveillance Requirements
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000336/LER-1996-005-01, :on 960212,discovered PEO Improperly Utilized to Replace Automatic Backwash Function of Svc Water Strainer Backwash Sys.Caused by Failure to Enter TS Action Statement. Revise Procedures for IST SWS Pump Operability |
- on 960212,discovered PEO Improperly Utilized to Replace Automatic Backwash Function of Svc Water Strainer Backwash Sys.Caused by Failure to Enter TS Action Statement. Revise Procedures for IST SWS Pump Operability
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000423/LER-1996-005-02, :on 960321,service Water Booster Pump Auto Start Discovered Disable.Caused by Inadequate Review.C/A: Bypass Jumper Removed & Mod Initiated |
- on 960321,service Water Booster Pump Auto Start Discovered Disable.Caused by Inadequate Review.C/A: Bypass Jumper Removed & Mod Initiated
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(s)(2) | | 05000423/LER-1996-005-03, :on 960321,design Noncompliance Noted for High Temp Automatic Start Feature of SWS Booster Pumps.Caused by Weakness in Design Control Process.Operating Procedures Revised |
- on 960321,design Noncompliance Noted for High Temp Automatic Start Feature of SWS Booster Pumps.Caused by Weakness in Design Control Process.Operating Procedures Revised
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) | | 05000336/LER-1996-006-01, :on 960207,service Water Pump Motor Flood Protection Not Provided.Caused by Inadequate Administrative Controls.Administrative Controls Established |
- on 960207,service Water Pump Motor Flood Protection Not Provided.Caused by Inadequate Administrative Controls.Administrative Controls Established
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000423/LER-1996-006-02, :on 960330,plant Shutdown Required by TS for AFW Containment Isolation Valves Declared Inoperable.Caused by Opened Valves Outside Containment.Unit Was Shutdown in Orderly Manner |
- on 960330,plant Shutdown Required by TS for AFW Containment Isolation Valves Declared Inoperable.Caused by Opened Valves Outside Containment.Unit Was Shutdown in Orderly Manner
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | | 05000423/LER-1996-007, :on 960403,containment Recirculation Spray, Quench Spray & Safety Injection Sys Were Outside Design Basis Due to Design Errors.Design Reviews of Rss,Qss,Si & Other Sys Will Be Performed |
- on 960403,containment Recirculation Spray, Quench Spray & Safety Injection Sys Were Outside Design Basis Due to Design Errors.Design Reviews of Rss,Qss,Si & Other Sys Will Be Performed
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii) | | 05000336/LER-1996-007, :on 960220,discovered RCS C/D Rate Exceeded TS Limit.Caused by Use of Wrong Temp Sensor.Plant Operating Procedures,Heatup/C/D Monitoring Computer Program & Operator Training Involving These Events Revised |
- on 960220,discovered RCS C/D Rate Exceeded TS Limit.Caused by Use of Wrong Temp Sensor.Plant Operating Procedures,Heatup/C/D Monitoring Computer Program & Operator Training Involving These Events Revised
| | | 05000423/LER-1996-007-01, :on 960403,CRS & Qs Sys Found Outside Design Basis Due to Design Errors.Restored Sys to Appropriate Design Basis Requirements Prior to Declaring Sys Inoperable |
- on 960403,CRS & Qs Sys Found Outside Design Basis Due to Design Errors.Restored Sys to Appropriate Design Basis Requirements Prior to Declaring Sys Inoperable
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000423/LER-1996-007-02, Forwards LER 96-007-02 Which Supplements Rept Submitted on 960502,per 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D), 10CFR50.73(a)(2)(vii)(B&D).Commitments in Response to Event, Encl | Forwards LER 96-007-02 Which Supplements Rept Submitted on 960502,per 10CFR50.73(a)(2)(ii)(B),10CFR50.73(a)(2)(v)(B&D), 10CFR50.73(a)(2)(vii)(B&D).Commitments in Response to Event, Encl | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) | | 05000336/LER-1996-008, :on 960222,concluded That Condition of Wire Mesh Screen Encl Over Two Containment Recirculation Suction Pipes Outside Design Basis.Caused by Const/Installation Error.Screen Encl Being Replaced |
- on 960222,concluded That Condition of Wire Mesh Screen Encl Over Two Containment Recirculation Suction Pipes Outside Design Basis.Caused by Const/Installation Error.Screen Encl Being Replaced
| | | 05000423/LER-1996-008-01, :on 960412,reactor Protection Sys Lead/Lag Time Constants Found non-conservative.Caused by Failure of Vendor to Identify Conservative Calibr Requirements.Tss Changed to Correctly Identify Direction of Conservatism |
- on 960412,reactor Protection Sys Lead/Lag Time Constants Found non-conservative.Caused by Failure of Vendor to Identify Conservative Calibr Requirements.Tss Changed to Correctly Identify Direction of Conservatism
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000423/LER-1996-009, :on 960423,inoperable Shutdown Margin Monitors from Low Count Rate Occurred Due to Inadequate Design Control.Reduced SMM Setpoint |
- on 960423,inoperable Shutdown Margin Monitors from Low Count Rate Occurred Due to Inadequate Design Control.Reduced SMM Setpoint
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000245/LER-1996-009-01, :on 960109,isolation Condenser Makeup Water Temperature Below Design Basis Limit,Determined.Caused by Inadequate Design Specification.Preliminary Assessment of non-ductile Failure of Isolation Condenser Sys Performed |
- on 960109,isolation Condenser Makeup Water Temperature Below Design Basis Limit,Determined.Caused by Inadequate Design Specification.Preliminary Assessment of non-ductile Failure of Isolation Condenser Sys Performed
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000336/LER-1996-009-01, :on 960216,post LOCA Contianment Pressure Prevented Timely Extraction of PASS Air Sample & H Sample. Caused by Inadequate Assessment of Revised Post LOCA Response Analysis.Implemented Design Change |
- on 960216,post LOCA Contianment Pressure Prevented Timely Extraction of PASS Air Sample & H Sample. Caused by Inadequate Assessment of Revised Post LOCA Response Analysis.Implemented Design Change
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000423/LER-1996-009-02, Submits Table of Commitments Re LER 96-009-02 Per 10CFR50.73(a)(2)(ii) | Submits Table of Commitments Re LER 96-009-02 Per 10CFR50.73(a)(2)(ii) | 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1996-010, :on 960222,identified That Containment Hydrogen Monitor Flow Could Not Be Established W/Containment at Atmospheric Pressure Due to Improper Setting of Sys Pressure Regulators.Sys Calib Procedure Will Be Revised |
- on 960222,identified That Containment Hydrogen Monitor Flow Could Not Be Established W/Containment at Atmospheric Pressure Due to Improper Setting of Sys Pressure Regulators.Sys Calib Procedure Will Be Revised
| | | 05000423/LER-1996-010-02, :on 960425,determined That Potential Failure Mode of Rod Control Sys Acopian Power Supplies Could Create Unanalyzed Condition.Caused by Inadequate Design Review. Reset Feature Will Be Deleted |
- on 960425,determined That Potential Failure Mode of Rod Control Sys Acopian Power Supplies Could Create Unanalyzed Condition.Caused by Inadequate Design Review. Reset Feature Will Be Deleted
| 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000336/LER-1996-011-01, :on 960222,required Time to Enter Mode 5 Exceeded.Caused by Effective Action Not Being Initiated to Revise SDC & Cooldown Rate Monitoring Procedures.Operating & Surveillance Procedures Will Be Revised |
- on 960222,required Time to Enter Mode 5 Exceeded.Caused by Effective Action Not Being Initiated to Revise SDC & Cooldown Rate Monitoring Procedures.Operating & Surveillance Procedures Will Be Revised
| | | 05000423/LER-1996-011-02, :on 960512,determined That Both Trains of CR Envelope Pressurization Sys Inoperable Due to Imbalance in air-conditioning Sys.Cr air-conditioning Sys Rebalanced.W/ |
- on 960512,determined That Both Trains of CR Envelope Pressurization Sys Inoperable Due to Imbalance in air-conditioning Sys.Cr air-conditioning Sys Rebalanced.W/
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000423/LER-1996-012, :on 960515,containment Leakage in Excess of TS Limits Noted,Due to Valve Leakage.Containment Spray Line Penetration 100 Flushed to Remove Any Boron Deposits.W/ |
- on 960515,containment Leakage in Excess of TS Limits Noted,Due to Valve Leakage.Containment Spray Line Penetration 100 Flushed to Remove Any Boron Deposits.W/
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1996-012-01, :on 960228,SIS Drain Stop Valves Failed to Meet Functional Requirements of Ts.Caused by Personnel Error & Inadequate Retest Requirements.C/A:Valve 2-SI-618 Modified & Safety Related Solenoid Valves Inspected |
- on 960228,SIS Drain Stop Valves Failed to Meet Functional Requirements of Ts.Caused by Personnel Error & Inadequate Retest Requirements.C/A:Valve 2-SI-618 Modified & Safety Related Solenoid Valves Inspected
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000423/LER-1996-012-02, :on 960515,containment Leakage Exceeded Tech Spec Limit.Caused by Boric Acid Residue.Performed Flush of Line to Remove Boron Deposits |
- on 960515,containment Leakage Exceeded Tech Spec Limit.Caused by Boric Acid Residue.Performed Flush of Line to Remove Boron Deposits
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000423/LER-1996-013, :on 960612,design Deficiency in Rhrs.Caused by Inconsideration That Failure Mode of RHS Flow Control Valves Could Create High RHS Heat Exchanger CCP Discharge Temps. Actuators for Heat Exchanger Valves,Modified |
- on 960612,design Deficiency in Rhrs.Caused by Inconsideration That Failure Mode of RHS Flow Control Valves Could Create High RHS Heat Exchanger CCP Discharge Temps. Actuators for Heat Exchanger Valves,Modified
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000336/LER-1996-013-01, :on 960314,assessed Wide Range Logarithmic Neutron Flux Monitors Nuclear Instrumentation Channels A,B,C & D as Inoperable Due to Potential Susceptability to Common Mode Failure.Replaced Failed Power Supply |
- on 960314,assessed Wide Range Logarithmic Neutron Flux Monitors Nuclear Instrumentation Channels A,B,C & D as Inoperable Due to Potential Susceptability to Common Mode Failure.Replaced Failed Power Supply
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000423/LER-1996-013-02, :on 960515,determined Design Deficiency in Residual Heat Removal System (Rhs).Caused by Original Plant Design.Corrective Actions Will Be Described in Supplement |
- on 960515,determined Design Deficiency in Residual Heat Removal System (Rhs).Caused by Original Plant Design.Corrective Actions Will Be Described in Supplement
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000336/LER-1996-014-01, :on 960311,weekly TS Surveillances Missed. Caused by Personnel Error W/Respect to Scheduling.C/A: Implemented Requirements of Surveillance Procedure Sp 2614A-3 |
- on 960311,weekly TS Surveillances Missed. Caused by Personnel Error W/Respect to Scheduling.C/A: Implemented Requirements of Surveillance Procedure Sp 2614A-3
| 10 CFR 50.73(a)(2)(i) | | 05000423/LER-1996-014-02, :on 960516,surveillances for Emergency Diesel Generator Performed During Operation,Versus Shutdown.Caused by Misinterpretation of Shutdown Stipulation.Surveillances Performed During Shutdown |
- on 960516,surveillances for Emergency Diesel Generator Performed During Operation,Versus Shutdown.Caused by Misinterpretation of Shutdown Stipulation.Surveillances Performed During Shutdown
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) | | 05000423/LER-1996-015-05, Forwards LER 96-015-05,documenting Event That Occurred at Plant,Unit 3 on 960610,per 10CFR50.73(a)(2)(ii)(B). Commitments Made within Ltr Submitted | Forwards LER 96-015-05,documenting Event That Occurred at Plant,Unit 3 on 960610,per 10CFR50.73(a)(2)(ii)(B). Commitments Made within Ltr Submitted | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) | | 05000423/LER-1996-015-04, Forwards LER 96-015-04,documenting Condition Determined at Unit 3 on 960610.Util Commitments in Response to Event Contained within Attachment 1 to Ltr | Forwards LER 96-015-04,documenting Condition Determined at Unit 3 on 960610.Util Commitments in Response to Event Contained within Attachment 1 to Ltr | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000336/LER-1996-015-01, :on 960312,failed to Perform Action Requirement for TS LCO 3.3.1.1.Caused by Failure to Recognize Applicability of TS During Abnormal Equipment Configuration. Revised Procedures |
- on 960312,failed to Perform Action Requirement for TS LCO 3.3.1.1.Caused by Failure to Recognize Applicability of TS During Abnormal Equipment Configuration. Revised Procedures
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000423/LER-1996-015-02, Forwards LER 96-015-02 Re Inadequate Electrical Separation Between Redundant Protection Trains Associated W/Reactor Trip Switches & Reactor Trip Breaker Indicating Lights | Forwards LER 96-015-02 Re Inadequate Electrical Separation Between Redundant Protection Trains Associated W/Reactor Trip Switches & Reactor Trip Breaker Indicating Lights | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000423/LER-1996-016-02, :on 960619,switchgear Cabinet in Noncompliance W/Seismic Design Basis & Subsequently Inadvertent Esfa Signal Occurred.Personnel Did Not Latch Known Seismic Latches as Required.Engaged Latches |
- on 960619,switchgear Cabinet in Noncompliance W/Seismic Design Basis & Subsequently Inadvertent Esfa Signal Occurred.Personnel Did Not Latch Known Seismic Latches as Required.Engaged Latches
| | | 05000336/LER-1996-016-01, :on 960312,common Power Supply Cable to 4 Condenser Pit Level Switches Found Improperly Connected. Caused by Inadequate Work Control.Cable Properly Connected & Trip Circuits Tested |
- on 960312,common Power Supply Cable to 4 Condenser Pit Level Switches Found Improperly Connected. Caused by Inadequate Work Control.Cable Properly Connected & Trip Circuits Tested
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000336/LER-1996-017, :on 960320,discovered That Hydrogen Monitoring Sys Does Not Meet Single Failure Criterion by Reg Guide 1.97.Caused by Failure to Adequately Consider Sys Design Basis Requirements.Design Change Modified |
- on 960320,discovered That Hydrogen Monitoring Sys Does Not Meet Single Failure Criterion by Reg Guide 1.97.Caused by Failure to Adequately Consider Sys Design Basis Requirements.Design Change Modified
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000423/LER-1996-017-02, :on 960621,determined Design Deficiency Existed in Tornado Protection Ventilation Dampers,Could Have Affected EDGs Following Tornado.Caused by Inadequate Original Plant Const Design.Procedure Revised |
- on 960621,determined Design Deficiency Existed in Tornado Protection Ventilation Dampers,Could Have Affected EDGs Following Tornado.Caused by Inadequate Original Plant Const Design.Procedure Revised
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | | 05000336/LER-1996-018-01, Forwards LER 96-018-01,documenting Condition That Was Discovered at Unit 2 on 960319.LER Suppl Provides Update on Analyses & Investigation of Condition.Attachment 1 Is Clarification of Original Commitment Associated W/Ler | Forwards LER 96-018-01,documenting Condition That Was Discovered at Unit 2 on 960319.LER Suppl Provides Update on Analyses & Investigation of Condition.Attachment 1 Is Clarification of Original Commitment Associated W/Ler | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000336/LER-1996-018, :on 960316,gaps Discovered in Encls Door Seals for Motor Control Ctrs B51 & B61.Caused by Weakness in Existing Program to Inspect & Verify Integrity of Environ Protective Barriers.Doors for MCC B51 & MCC B61 Replaced |
- on 960316,gaps Discovered in Encls Door Seals for Motor Control Ctrs B51 & B61.Caused by Weakness in Existing Program to Inspect & Verify Integrity of Environ Protective Barriers.Doors for MCC B51 & MCC B61 Replaced
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) | | 05000423/LER-1996-019-02, :on 960627,RCS PORV Block Valves Were Determined to Be Unable to Perform Intended Safety Functions.Caused by Structural Design Deficiency.C/A Will Be Provided in Supplement to Rept |
- on 960627,RCS PORV Block Valves Were Determined to Be Unable to Perform Intended Safety Functions.Caused by Structural Design Deficiency.C/A Will Be Provided in Supplement to Rept
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) |
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