:on 970131,failure to Exert Best Efforts to Restore Radwaste Effluent Line Radiation Monitor to Operable Status Occurred.Caused by Failure to Provide Clear Management Expectations.Management Will Be Provided| ML20138Q188 |
| Person / Time |
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| Site: |
Millstone  |
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| Issue date: |
03/03/1997 |
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| From: |
Robert Walpole NORTHEAST NUCLEAR ENERGY CO. |
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| To: |
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| Shared Package |
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| ML20138Q161 |
List: |
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| References |
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| LER-97-006-01, LER-97-6-1, NUDOCS 9703060194 |
| Download: ML20138Q188 (3) |
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROtfED BY OMB NO. 3150-0104 (4 95)
EXPlRES 44/30/98 NoYaEtSoUc$r'c'[cm No")sT [oNs FIo T[oISS L
k'ari! T,stF?is EfoPlaWrs4!N=5nt[s?,ei LICENSEE EVENT REPORT (LER) 5 s TuctifatJM? nLi&"~^t'n=o**^ano'Isila
^*?a2/.'M*aaf.ifas (cWu'" " '
(See reverse for required number of digits / Characters for eaCh block) l FOCILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Millstone Nuclear Power Station Unit 1 05000245 1 of 3 TifLE 64) 1 Failure to Exert Best Efforts to Restore the Radwaste Effluent Line Radiation Monitor to Operable Status EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
I MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR F AcluTY NAME DOCKET NUMBER NUMBER 1
"' " ~^"'
01 31 97 97 006 00 03 03 97 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR i: (Check one or more) (11)
MODE (9)
N 20.2201(b) 20.2203(aH2)(v)
X 50 73(aH2Hi) 50.73(a)(2)(viii>
POWER 20.2203(a)(1) 20.2203(aH3Hi) 50.73(aH2)(ii) 50.73(aH2)(x)
LEVEL (10) 000 20.2203(a)(2Hi) 20.2203(a)t3)(ii) 50.73(a)(2)(iii) 73.71 20.2203(a)(2Hid 20.2203(a)(4) 50.73(a)(2Hav)
OTHER
.,..,o,.
i or in NRC Form 366A 20.2203(a)(2Hiv) 50.36(c)(2) 50.73(aH2Hvii)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (include Area Codel Robert W. Walpole, MP1 Nuclear Licensing Manager (860)440-2191 i
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORrABLE
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR SUBMISSION f
YES NO (if yes, complete EXPECTED SUBMISSION DATE).
ABSTRACT (Limit to 1400 spaces, i e., approximately 15 singit,-spaced typewritten knes) (16)
On January 31,1997, with the plant in the Cold Shutdown condition, it was determined that "best efforts" were not being demonstrated to restore the Radwaste Effluent Line Radiation Monitor to an operable status. Technical Specification (TS) Section 3.8.A, Action 3 states, " exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Report why the inoperability was not corrected in a timely manner." The Radwaste Effluent Line Radiation Monitor has remained inoperable since June 5, 1996, due to issues addressed in previous LERs: 96-043-00 on inadequate time response testing; 96-053-00 on inadequate source checks; and 96-065-00 and 97-001-00 on non-conservative setpoints due to draining the discharge piping. Since these conditions were not resolved using best efforts, as specified in TS, this event is reportable as a condition prohibited by the plant's TS. The cause of this event was failure to provide clear management expectations of what constitutes "best efforts" and inadequate prioritization of work required to restore the Radwaste Effluent Line Radiation Monitor to an operable status. Corrective actions include providing guidance for TS "best efforts" and returning the Radwaste Effluent Line Radiation Monitor to an operable status. The safety significance of this event is low since required TS compensatory actions were in place the entire time. Therefore, no safety consequences resulted from this event.
9703060194 970303 PDR ADOCK 05000245 S
PDR
'NRC FORM 316A U.S. NUCLEAR REGULATORY COMMisslON 14 95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME t1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
YEAR SEQUENTIAL REVISION Millstone Nuclear Power Station Unit 1 05000245 NUMBER NUMBER 2 of 3 97 006 00 TEXT (11more space is required, use additionalcopies of NRC Form 366A) til) i 1.
Descrintion of Event i
On January 31,1997, at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, with the plant in the Cold Shutdown condition, it was determined i
that "best efforts" were not being demonstrated to restore the Radwaste Effluent Line Radiation Monitor to an operable status. TS Section 3.8.A, Action 3 states, " exert best efforts to restore the inoperable monitor l
to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Report why the inoperability was not corrected in a timely manner." The Radwaste Effluent Line radiation monitor has l
remained inoperable since June 5,1996, due to a variety of issues. Since these issues were not resolved using best efforts, as specified in TS, this event is reportable pursuant to 10CFR50.73(a)(2)(i)(B), as a l
l condition prohibited by the plant's Technical Specifications.
The recent inoperability of the Radweste Effluent Line Radiation Monitor can be summarized by the following Millstone 1 reportable events: on January 10, 1997, potential failure of the Radwaste Effluent Line Radiation Monitor to isolate the discharge when required due to leaking isolation valves (LER 97-001-00); on December 12,1996, failure to adjust the Radwaste Effluent Line Radiation Monitor setpoints in accordance i
i with TS was identified (LER 96-065-00); on October 2,1996, it was determined that inadequate radiation monitor source checks had been performed (LER 96-053 00); and on June 5,1996, it was determined that the response time testing requirements of the TS calibration definition had not been met (LER 96-043-00).
g Although time response testing was completed on December 11,1996, and adequate source checks have now been proceduralized, the monitor remains inoperable due to design issues identified during the events concerning the improper setpoints and leaking isolation valves. Completion of LER 96-065-00 commitment to revise the discharge procedure by March 31,1997, to ensure a proper background level is accounted for while discharging effluents, is scheduled to return the monitor to an operable status. Due to the length of time that the monitor has been inoperable, including several periods of inactivity, Northeast Nuclear Energy Company (NNECO) has determined that best efforts have not been demonstrated to return the monitor to an operable status. The monitor routinely rerr.ained in a functional status during liquid effluent discharges.
1 t
11.
Cause of Event
The cause of this event was failure to provide clear management expectations of what constitutes "best i
efforts" and inadequate prioritization of work required to restore the Radwaste Effluent Line Radiation Monitor to an operable status. Prioritization and scheduling of tasks required to exit the radiation monitor "best efforts" LCO were based upon perceived impact on plant operations, vice the literal requirements of the best efforts Technical Specifications.
Ill. Analysis of Event i
]
The Radwuste Effluent Line Radiation Monitor is provided to monitor and control, as applicable, the release j
i of radioactive material in liquid effluents during actual or potential releases. The operability and use of this j
monitor provides a means of compliance with 10CFR20; 10CFR50 Appendix A, General Design Criteria 60, 63 and 64; as well as Regulatory Guides 1.21,1.97,4.15 and 8.8. Per Updated Final Safety Analysis Report (UFSAR) Section 11.5.1, monitoring the radiation level in the radioactive liquid discharge effluents and associated actions are non safety related functional requirements.
The Liquid Radwaste Effluent Radiation Monitor continuously monitors, measures and records the activity l
level in the liquid radioactive waste discharged from the station via the liquid effluent line to the discharge
)
canal to Long Island Sound. These liquids are combined with dilution flow that will result in concentrations i)
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'NRC FOkM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)
UCENSEE EVENT REPORT (LER)
TEXT CONTINUATION 1
l FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE 13) l YEAR
. SEQUENilAL HEVISION Millstone Nuclear Power Station Unit 1 05000245 NUMBER NUMBER 3 of 3 97 006 00 1
1 TEXT (11more space is required, use additional copies of NRC Form 366A) (17) r less than allowable limits at the plant discharge. The radioactive waste monitor will alarm in the main control l
room when radiation levels reach the high setpoint. The monitor on this discharge line will also alarm in the main control room if the established Hi-Hi setpoint is exceeded and close the discharge valves in the line, prior to reaching allowable release limits. The system is composed of a shielded scintillation detector positioned on a section of the process liquid piping prior to leaving the radwaste building.
i TS section 3.8.A requires that the Liquid Radwaste Effluent Line radiation monitor be operable and in service on a continuous, uninterrupted basis, if the radiation monitor is not operable, effluent releases may continue provided that best efforts are made to restore the monitor to an operable status and that independent verification of the discharge valving, release rate calculations, and samples are conducted. Since "best l
efforts" were not demonstrated in accordance with the associated TS action statement, as described above, this event is reportable pursuant to 10CFR50.73(a)(2)(i)(B), as a condition prohibited by the plant's Technical Specifications.
The safety significance of this event is low since required TS compensatory actions were in place the entire time. Therefore, no consequences resulted from this event.
Equipment restoration efforts were focused on operational impact to the plant. Since the Radwaste Effluent Line Radiation Monitor was initially inoperable for failure to perform time response testing, no clear line of responsibility was assigned to restore the instrument. The Radweste Effluent Line Radiation Monitor routinely remained capable of performing its intended function, and TS permitted continued radwaste discharges with minimal additional actions; therefore although best efforts were required, little urgency j
l existed to restore the monitor to an operable status. This complacency regarding Radwaste Effluent Line Radiation Monitor inoperability resulted in the failure to schedule and prioritize the tasks necessary to restore the monitor to an operable status.
IV. Corrective Action
NNECO will provide management guidance on the requirements for meeting TS "best efforts" action i
statement which will be communicated to appropriate personnel prior to March 31,1997.
NNECO will ensure that the Radwaste Effluent Line Radiation Monitor is returned to an operable status consistent with best efforts prior to March 31,1997.
V.
Additional Information
Similar Events None Manufacturer Data Not Applicable i
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| 05000245/LER-1997-001-02, :on 970110,liquid Radwaste Effluent Radiation Monitor Declared Inoperable Due to Leaking Automatic Isolation Valves.Valves Repaired |
- on 970110,liquid Radwaste Effluent Radiation Monitor Declared Inoperable Due to Leaking Automatic Isolation Valves.Valves Repaired
| 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-1997-001, Forwards LER 97-001-00,documenting Event That Occurred at Millstone Nuclear Power Station,Unit 1 on 970110.Util Commitments Made within Ltr,Listed | Forwards LER 97-001-00,documenting Event That Occurred at Millstone Nuclear Power Station,Unit 1 on 970110.Util Commitments Made within Ltr,Listed | 10 CFR 50.73(a)(2)(i) | | 05000423/LER-1997-001, Submits Commitments Re LER 97-001-00,documenting Condition Determined at Plant on 970104 | Submits Commitments Re LER 97-001-00,documenting Condition Determined at Plant on 970104 | 10 CFR 50.73(a)(2)(i) | | 05000423/LER-1997-001-01, :on 970104,discovered Lack of Verbatim Compliance W/Ts SRs for 125 Volt Batteries & Battery Chargers.Caused by Misconception That Performing Surveillances Was Acceptable.Revised Procedures |
- on 970104,discovered Lack of Verbatim Compliance W/Ts SRs for 125 Volt Batteries & Battery Chargers.Caused by Misconception That Performing Surveillances Was Acceptable.Revised Procedures
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) | | 05000423/LER-1997-002, :on 970108,torquing of Battery Connections Not Performed as Part of Connection Tightness Checks Occurred. Caused by Lack of Effective Verification & Validation of Maint Procedure.Procedure Revised |
- on 970108,torquing of Battery Connections Not Performed as Part of Connection Tightness Checks Occurred. Caused by Lack of Effective Verification & Validation of Maint Procedure.Procedure Revised
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) | | 05000245/LER-1997-002, Forwards LER 97-002-00 Which Documents an Event That Occurred at Mnps,Unit 1 on 970114,per 10CFR50.73(a)(2)(iv). Commitments Made,Listed | Forwards LER 97-002-00 Which Documents an Event That Occurred at Mnps,Unit 1 on 970114,per 10CFR50.73(a)(2)(iv). Commitments Made,Listed | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000245/LER-1997-002-02, :on 970114,inadvertent Shutdown Cooling Isolation Occurred During Sys Removal from Svc for Maint. Caused by Inadequacy in Preparation of Clearance Required to Perform Maint.Individuals Involved Have Been Counseled |
- on 970114,inadvertent Shutdown Cooling Isolation Occurred During Sys Removal from Svc for Maint. Caused by Inadequacy in Preparation of Clearance Required to Perform Maint.Individuals Involved Have Been Counseled
| 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) | | 05000336/LER-1997-002, Forwards LER 97-002-00 Which Documents an Event That Occurred on 970108,per 10CFR50.73(a)(2)(ii).Commitments Made within Ltr,Listed | Forwards LER 97-002-00 Which Documents an Event That Occurred on 970108,per 10CFR50.73(a)(2)(ii).Commitments Made within Ltr,Listed | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000336/LER-1997-002-01, :on 970108,damper 2-HV-210 Could Not Be Manually Operated within Ten Minutes as Required in Accident Analysis.Caused by Inadequate Evaluation of Mechanical Binding.Damper Was Placed in Fail Open Position |
- on 970108,damper 2-HV-210 Could Not Be Manually Operated within Ten Minutes as Required in Accident Analysis.Caused by Inadequate Evaluation of Mechanical Binding.Damper Was Placed in Fail Open Position
| 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-1997-003, Forwards LER 97-003-00 Which Documents Condition That Was Determined at Mnps,Unit 3 on 970113,per 10CFR50.73(a)(2)(ii) (B).List of Commitments,Encl | Forwards LER 97-003-00 Which Documents Condition That Was Determined at Mnps,Unit 3 on 970113,per 10CFR50.73(a)(2)(ii) (B).List of Commitments,Encl | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000423/LER-1997-003-01, :on 970113,potential for Recirculation Spray Sys Piping Failure Occurred Due to RSS Pump Stopping & Restarting During Accident Conditions.Performed Evaluation of RSS Water Column Separation Issue |
- on 970113,potential for Recirculation Spray Sys Piping Failure Occurred Due to RSS Pump Stopping & Restarting During Accident Conditions.Performed Evaluation of RSS Water Column Separation Issue
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000336/LER-1997-003-01, Corrected Page One to LER 97-003-01:on 961216,discovered Discrepancy in Plant Procedure Utilized to Perform Periodic Insp of Fire Protection Sys Smoke Detectors.Caused by Failure to Properly Incorporate Ts.Ts Partially Revis | Corrected Page One to LER 97-003-01:on 961216,discovered Discrepancy in Plant Procedure Utilized to Perform Periodic Insp of Fire Protection Sys Smoke Detectors.Caused by Failure to Properly Incorporate Ts.Ts Partially 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)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | | 05000245/LER-1997-003, Forwards LER 97-003-00 Which Documents an Event That Occurred at Mnps,Unit 1 on 970306,per 10CFR50.73(a)(2)(i). Commitments Made within Ltr,Listed | Forwards LER 97-003-00 Which Documents an Event That Occurred at Mnps,Unit 1 on 970306,per 10CFR50.73(a)(2)(i). Commitments Made within Ltr,Listed | 10 CFR 50.73(a)(2)(i) | | 05000245/LER-1997-003-02, :on 970306,svc Water Effluent Was Not Monitored Per Requirements of Ts.Caused by Inadequate Design Change Package.Procedures to Ensure That SW Effluent from Reactor Bldg Operated within Design Basis Revised |
- on 970306,svc Water Effluent Was Not Monitored Per Requirements of Ts.Caused by Inadequate Design Change Package.Procedures to Ensure That SW Effluent from Reactor Bldg Operated within Design Basis 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)(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-1997-004-01, :on 970123,violation of TS 3.1.2.3 Requirement for Number of High Pressure Safety Injection Pumps Capable of Injecting Into RCS Occurred.Caused by Personnel Error. HPSI Pumps Have Been Revised |
- on 970123,violation of TS 3.1.2.3 Requirement for Number of High Pressure Safety Injection Pumps Capable of Injecting Into RCS Occurred.Caused by Personnel Error. HPSI Pumps Have Been Revised
| 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 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) | | 05000245/LER-1997-004-01, Forwards LER 97-004-01,documenting Closure of Commitment B16213-1.Includes Commitments Made within This Ltr | Forwards LER 97-004-01,documenting Closure of Commitment B16213-1.Includes Commitments Made within This Ltr | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000245/LER-1997-004-02, :on 970127,RBCCW Containment Isolation Sys Single Failure Vulnerability Occurred.Caused by Failure to Adequately Establish Design Basis.No Immediate CA Are Required |
- on 970127,RBCCW Containment Isolation Sys Single Failure Vulnerability Occurred.Caused by Failure to Adequately Establish Design Basis.No Immediate CA Are Required
| 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) 10 CFR 50.73(a)(2) | | 05000245/LER-1997-004, :on 970127,RBCCW Containment Isolation Valve May Not Close within Specified Time.Caused by Failure to Adequately Establish Design Basis.Plant Is in Cold Shutdown W/Reactor Defueled |
- on 970127,RBCCW Containment Isolation Valve May Not Close within Specified Time.Caused by Failure to Adequately Establish Design Basis.Plant Is in Cold Shutdown W/Reactor Defueled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) | | 05000423/LER-1997-004, :on 970114,lack of Verbatim Compliance with TS Surveillance Requirements for Molded Case Circuit Breakers Occurred.Caused by Addl Lack of Verbatim Compliance. Corrected 18 Month Surveillances Will Be Performed |
- on 970114,lack of Verbatim Compliance with TS Surveillance Requirements for Molded Case Circuit Breakers Occurred.Caused by Addl Lack of Verbatim Compliance. Corrected 18 Month Surveillances Will Be Performed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) | | 05000245/LER-1997-005-01, Forwards LER 97-005-01,documenting Closure of Commitment B16236-2 & B16236-3,including Commitments Made within Ltr | Forwards LER 97-005-01,documenting Closure of Commitment B16236-2 & B16236-3,including Commitments Made within Ltr | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000245/LER-1997-005, :on 970115,discovered That Radwaste Storage Bldg Vent Exhaust Fan HVE-14 Discharges Directly to Atmosphere.Caused by Inadequate Design Review.Operation of Exhaust Fan HVE-14 Was Prevented Immediately |
- on 970115,discovered That Radwaste Storage Bldg Vent Exhaust Fan HVE-14 Discharges Directly to Atmosphere.Caused by Inadequate Design Review.Operation of Exhaust Fan HVE-14 Was Prevented Immediately
| 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)(iii) 10 CFR 50.73(a)(2)(viii) | | 05000336/LER-1997-005-02, :on 970204,inservice Test Instrumentation Did Not Meet Ansi/Asme Chapter XI Requirements.Caused by Inadequate Administrative Structure for IST Program. Procedure to Administer IST Program Was Implemented |
- on 970204,inservice Test Instrumentation Did Not Meet Ansi/Asme Chapter XI Requirements.Caused by Inadequate Administrative Structure for IST Program. Procedure to Administer IST Program Was Implemented
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000336/LER-1997-005, Forwards LER 97-005-00 Which Documents Event That Occurred at Mnps,Unit 2 on 970204.Commitments Made,Listed | Forwards LER 97-005-00 Which Documents Event That Occurred at Mnps,Unit 2 on 970204.Commitments Made,Listed | 10 CFR 50.73(a)(2)(i) | | 05000423/LER-1997-005, Corrects Numbering Inconsistency in Commitments Addressing LER 97-005-00 | Corrects Numbering Inconsistency in Commitments Addressing LER 97-005-00 | | | 05000245/LER-1997-006-01, :on 970131,failure to Exert Best Efforts to Restore Radwaste Effluent Line Radiation Monitor to Operable Status Occurred.Caused by Failure to Provide Clear Management Expectations.Management Will Be Provided |
- on 970131,failure to Exert Best Efforts to Restore Radwaste Effluent Line Radiation Monitor to Operable Status Occurred.Caused by Failure to Provide Clear Management Expectations.Management Will Be Provided
| 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) | | 05000423/LER-1997-006, :on 970117,RHR Suction Isolation Valves Open But Not Under Administrative Control as Required in Mode 4 by TS SR 4.6.1.1.a.Caused by Failure to Identify Conflict Between Requirements.Rhr Required Position Determined |
- on 970117,RHR Suction Isolation Valves Open But Not Under Administrative Control as Required in Mode 4 by TS SR 4.6.1.1.a.Caused by Failure to Identify Conflict Between Requirements.Rhr Required Position Determined
| 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-1997-006-01, Forwards LER 97-006-01 Per 10CFR50.73(a)(2)(i).Util Commitments in Response to 970117 Event Contained within Attachment 1 | Forwards LER 97-006-01 Per 10CFR50.73(a)(2)(i).Util Commitments in Response to 970117 Event Contained within Attachment 1 | 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1997-006-02, :on 970211,main Steam Line Break Inside Containment Event Could Result in Exceeding Design Pressure of Primary Containment During Certain Scenarios.Caused by Inadequate Evaluation.Ca Will Be Implemented |
- on 970211,main Steam Line Break Inside Containment Event Could Result in Exceeding Design Pressure of Primary Containment During Certain Scenarios.Caused by Inadequate Evaluation.Ca Will Be Implemented
| 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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000245/LER-1997-006, Forwards LER 97-006-00,documenting Condition That Was Discovered at Millstone Nuclear Station,Unit 1 on 970131, Per 10CFR50.73(a)(2)(i).Util Commitments Made within Ltr, Listed | Forwards LER 97-006-00,documenting Condition That Was Discovered at Millstone Nuclear Station,Unit 1 on 970131, Per 10CFR50.73(a)(2)(i).Util Commitments Made within Ltr, Listed | 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1997-006, Forwards LER 97-006-00 Which Documents an Event That Occurred on 970211.Commitments Made within Ltr,Listed | Forwards LER 97-006-00 Which Documents an Event That Occurred on 970211.Commitments Made within Ltr,Listed | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000245/LER-1997-007, Forwards LER 97-007-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970131,per 10CFR50.73(a)(2)(i) & 10CFR50.73(a)(2)(ii). Util Commitments Made within Ltr,Listed | Forwards LER 97-007-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970131,per 10CFR50.73(a)(2)(i) & 10CFR50.73(a)(2)(ii). Util Commitments Made within Ltr,Listed | 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000336/LER-1997-007-02, :on 970308,inadequate Surveillance Procedure Used for Verifying Operability of RCS Vents.Caused by Failure to Incorporate TS SRs Into Plant Surveillance Procedures.Revised Surveillance Procedure |
- on 970308,inadequate Surveillance Procedure Used for Verifying Operability of RCS Vents.Caused by Failure to Incorporate TS SRs Into Plant Surveillance Procedures.Revised Surveillance Procedure
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000336/LER-1997-007, Provides List of Commitments for LER 97-007-00 Re Event That Occurred on 970308 | Provides List of Commitments for LER 97-007-00 Re Event That Occurred on 970308 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000423/LER-1997-007, :on 970123,non-conservative Assumptions Used in TSs Shutdown Margin Curve Identified.Caused by Lack of Procedures for Generation & Documentation of Reactor Operational Info.Engineering Procedure Will Be Revised |
- on 970123,non-conservative Assumptions Used in TSs Shutdown Margin Curve Identified.Caused by Lack of Procedures for Generation & Documentation of Reactor Operational Info.Engineering Procedure Will Be Revised
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) | | 05000245/LER-1997-008, Forwards LER 97-008-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970203,per 10CFR50.73(a)(2)(ii).Util Commitments Made within Ltr,Listed | Forwards LER 97-008-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970203,per 10CFR50.73(a)(2)(ii).Util Commitments Made within Ltr,Listed | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000423/LER-1997-008, :on 970124,TS 3.0.3 Action Statement for MSIV Closure Was Entered Due to TS Being Inconsistent W/Msiv Safety Function & Design.Submitted Proposed License Amend Request Ptscr 3-13-95 |
- on 970124,TS 3.0.3 Action Statement for MSIV Closure Was Entered Due to TS Being Inconsistent W/Msiv Safety Function & Design.Submitted Proposed License Amend Request Ptscr 3-13-95
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1997-008, Forwards LER 97-008-00,documenting Event Occurred at Unit 2 on 970310.Commitments Made within Ltr Listed as Submitted | Forwards LER 97-008-00,documenting Event Occurred at Unit 2 on 970310.Commitments Made within Ltr Listed as Submitted | 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1997-008-02, :on 970310,repts Review Facility Compliance W/ GL 96-01 for Reactor Protective Sys Received.Caused by Inadequate Program to Ensure Surveillance Procedures Fully Implement TS Requirements.Procedures Revised |
- on 970310,repts Review Facility Compliance W/ GL 96-01 for Reactor Protective Sys Received.Caused by Inadequate Program to Ensure Surveillance Procedures Fully Implement TS Requirements.Procedures Revised
| 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)(viii) | | 05000245/LER-1997-008-01, :on 970203,discovered Starting Air Sys Operating Outside Design Basis.Caused by Failure to Properly Identify & Verify Design Basis.Design Basis Established & Documented in FSAR |
- on 970203,discovered Starting Air Sys Operating Outside Design Basis.Caused by Failure to Properly Identify & Verify Design Basis.Design Basis Established & Documented in FSAR
| 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)(viii) 10 CFR 50.73(a)(2) | | 05000336/LER-1997-009, Forwards LER 97-009-00,which Documents an Event That Occurred on 970325.Commitments Made within Ltr,Submitted | Forwards LER 97-009-00,which Documents an Event That Occurred on 970325.Commitments Made within Ltr,Submitted | 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1997-009-02, :on 970325,insufficient ESFAS Surveillance Testing,Per GL 96-01 Review Occurred.Caused by Inadequate Program to Ensure Surveillance Procedures Fully Implement TS Requirements.Procedures Will Be Revised |
- on 970325,insufficient ESFAS Surveillance Testing,Per GL 96-01 Review Occurred.Caused by Inadequate Program to Ensure Surveillance Procedures Fully Implement TS Requirements.Procedures Will Be Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000245/LER-1997-009-01, :on 970212,reactor low-low Level ECCS & Primary Containment Initiation Setpoints Were Not Conservative. Caused by Deficient Setpoint Methodology.Calculations Will Be Revised & TS Change Initiated |
- on 970212,reactor low-low Level ECCS & Primary Containment Initiation Setpoints Were Not Conservative. Caused by Deficient Setpoint Methodology.Calculations Will Be Revised & TS Change Initiated
| 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)(iii) | | 05000245/LER-1997-009, Forwards LER 97-009-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970212.Util Commitments Made within Ltr,Listed | Forwards LER 97-009-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970212.Util Commitments Made within Ltr,Listed | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000336/LER-1997-009-01, :on 970325,insufficient ESFAS Surveillance Testing,Per GL 96-01,noted.Caused by Inadequate Program to Ensure Sps Fully Implement TS Requirements.Operational Surveillances Will Be Revised |
- on 970325,insufficient ESFAS Surveillance Testing,Per GL 96-01,noted.Caused by Inadequate Program to Ensure Sps Fully Implement TS Requirements.Operational Surveillances Will Be Revised
| 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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000423/LER-1997-009-01, Forwards LER 97-009-01,documenting Condition Originally Determined Reportable at Unit 3 on 970123.Util Commitments in Response to Event Contained within Attachment 1 to Ltr | Forwards LER 97-009-01,documenting Condition Originally Determined Reportable at Unit 3 on 970123.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) | | 05000336/LER-1997-010, Forwards LER 97-010-00,documenting Event Occurred at Unit 2 on 970112.Commitments Made within Ltr Listed | Forwards LER 97-010-00,documenting Event Occurred at Unit 2 on 970112.Commitments Made within Ltr Listed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000423/LER-1997-010, :on 970129,electrical Calculation Discrepancies Identified in Min Voltage Analysis for Class 1E Electrical Sys.Caused by Lack of Configuration Mgt for Comprehensive Calculation Program.Program Being Revised |
- on 970129,electrical Calculation Discrepancies Identified in Min Voltage Analysis for Class 1E Electrical Sys.Caused by Lack of Configuration Mgt for Comprehensive Calculation Program.Program Being 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 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) | | 05000245/LER-1997-010-01, :on 970214,determined LLRT Pressure Being Used May Be Less than Accident Pressure.Caused by Weakness in Mgt Commitment to App J Program.Llrts Modified |
- on 970214,determined LLRT Pressure Being Used May Be Less than Accident Pressure.Caused by Weakness in Mgt Commitment to App J Program.Llrts Modified
| 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)(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 | | 05000245/LER-1997-010, Forwards LER 97-010-00,documenting Event Occurred at Unit 1 on 970214.Commitments Made within Ltr Submitted as Listed | Forwards LER 97-010-00,documenting Event Occurred at Unit 1 on 970214.Commitments Made within Ltr Submitted as Listed | 10 CFR 50.73(a)(2)(i) | | 05000336/LER-1997-010-02, :on 970112,heavy Dummy Fuel Assembly & Handling Tool Weight Exceeded TS Limit Occurred.Caused by Weight of Handling Tool Never Considered to Be Part of Load.Temporary Measure & Appropriate Procedures Revised |
- on 970112,heavy Dummy Fuel Assembly & Handling Tool Weight Exceeded TS Limit Occurred.Caused by Weight of Handling Tool Never Considered to Be Part of Load.Temporary Measure & Appropriate 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)(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) |
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