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| | issue date = 07/07/1998 | | | issue date = 07/07/1998 |
| | title = LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys | | | title = LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys |
| | author name = VERRILLI M | | | author name = Verrilli M |
| | author affiliation = CAROLINA POWER & LIGHT CO. | | | author affiliation = CAROLINA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:NRC FORM 366 H.B5)U.S.NU EAR REGULATORY COMMISSION LXCENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)APPROVED BY OMB NO.3150.0104 EXPIRES 04/30/96 ESTIMATED BUROEH PER RESPOt(SE TO COMPLY yt(TH THIS MAt(DATORY INFORMATION COllECTIOII REOUEST: 50O HRS.REPORTED lESSONS LEARNED ARE (NCORPORATEO lt(TO THE UCENSLNG PROCESS ANO FEO BACK TO U(OUSTRY.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION ANO RECORDS MANAGEMENT BRANCH IT4)F33).US.NUCLEAR REGULATORY COMMISSION, WASHINGTON. | | {{#Wiki_filter:NRC FORM 366 U.S. NU EAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150.0104 H.B5) EXPIRES 04/30/96 ESTIMATED BUROEH PER RESPOt(SE TO COMPLY yt(TH THIS MAt(DATORY INFORMATION COllECTIOII REOUEST: 50O HRS. REPORTED lESSONS LEARNED ARE LXCENSEE EVENT REPORT (LER) (NCORPORATEO lt(TO THE UCENSLNG PROCESS ANO FEO BACK TO U(OUSTRY. |
| DC 20555()00), AND TO THE PAPERWORK REDUCTION PROJECT gl50.010().OFFICE OF h(ANAGEh'IENT ANO BUDGET, WASH(t(GTON, DC 20503.FACILITY NAME (1I Harris Nuclear Plant Unit-1 DOCKET NUMBER (2)50-400 PAGE (3)1OF3 TITLE (4)Inoperable Main Feedwater Isolation Valves caused by cold weather conditions. | | FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION ANO RECORDS MANAGEMENT BRANCH IT4) F33). US. NUCLEAR REGULATORY COMMISSION, (See reverse for required number of WASHINGTON. DC 20555()00), AND TO THE PAPERWORK REDUCTION PROJECT gl50. |
| EVENT DATE (5)LER NUMBER (6)REPORT DATE{7)OTHER FACILITIES INVOLVED (6)MONTH OAY YEAR SEQUENTIAL REVISION NUMBER NUMBER MONTH DAY FACIL(TY NAME DOCKET NUMBER 2 7 OPERATING MODE (9)97 97-002-01 THIS REPORT IS SUBMITTED PUR 20.2201(b) 07 07 98 FACIUTY NAME DOCKET NUMBER 05000 SUANT TO THE REQUIREMENTS OF 10 CFR E: (Chock ona or more)(11)50.73(a)(2)(viii) 20.2203(a) | | digits/characters for each block) 010(). OFFICE OF h(ANAGEh'IENT ANO BUDGET, WASH(t(GTON, DC 20503. |
| (2)(v)50.73(a)(2)(i)POWER LEVEL (10)100o 20.2203(a) | | FACILITY NAME (1I DOCKET NUMBER (2) PAGE (3) |
| (1)20.2203(a) | | Harris Nuclear Plant Unit-1 50-400 1OF3 TITLE (4) |
| (2)(i)20.2203(a) | | Inoperable Main Feedwater Isolation Valves caused by cold weather conditions. |
| (2)(ii)20.2203(a) | | EVENT DATE (5) LER NUMBER (6) REPORT DATE {7) OTHER FACILITIES INVOLVED (6) |
| (2)(iii)20.2203(a) | | FACIL(TY NAME DOCKET NUMBER SEQUENTIAL REVISION MONTH OAY YEAR MONTH DAY NUMBER NUMBER FACIUTY NAME DOCKET NUMBER 2 7 97 97 002 01 07 07 98 05000 OPERATING THIS REPORT IS SUBMITTED PUR SUANT TO THE REQUIREMENTS OF 10 CFR E: (Chock ona or more) (11) |
| (2)(iv)20.2203(a) | | MODE (9) 20.2201(b) 20.2203(a) (2) (v) 50.73(a) (2) (i) 50.73(a)(2)(viii) 20.2203(a) (1) 20.2203(a) (3) (i) 50.73(a)(2)(ii) 50.73(a)(2)(x) |
| (3)(i)20.2203(a) | | POWER 100o LEVEL (10) 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) OTHER 20.2203(a) (2) (iii) 50.36(c)(1) 50.73(a) {2){v) Specify ln Abstract be(ow or in NRC Form 366A 20.2203(a) (2) (iv) 50.36(c) (2) 50.73(a)(2)(vii) |
| (3)(ii)20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv)50.73(a){2){v)50.73(a)(2)(vii) 50.73(a)(2)(x) 73.71 OTHER Specify ln Abstract be(ow or in NRC Form 366A NAME LICENSEE CONTACT FOR THIS LER (12)TELEPHONE NUMBER (rncrvde Area Code)Michael Verrilli Sr.Analyst-Licensing (919)362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM CONIPONENT MANUFACTURER REPORTABLE TO NPROS CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPROS VF FAN J127 SUPPLEMENTAL REPORT EXPECTED{14)YES (If yos, complete EXPECTED SUBMISSION DATE).X NO EXPECTED SUBMISSION DATE{16)MONTH OAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)(16)On February 7, 1997, with the plant operating in Mode 1 at 100%power, investigation determined that cold weather conditions resulted in the Main Feedwater Isolation Valves (MFIVs)being potentially inoperable during a period from January 17, 1997 through January 20, 1997.The MFIVs serve as containment isolation valves and are required to stroke closed in 10 seconds or less.to provide feedwater isolation in the event of a main steam line break or spurious opening of a feedwater regulating valve.Based on purchase specification documents and discussions with the MFIV vendor, a minimum operating temperature of 60 degrees exists to ensure that the MFIVs will stroke in the required 10 seconds.The" MFIV actuators are hydraulic to open and shut with nitrogen pressure, but even the shut sequence utilizes hydraulic oil operation. | | LICENSEE CONTACT FOR THIS LER (12) |
| Therefore, with actuator temperature below 60 degrees the hydraulic oil may be too viscous to provide a valve stroke time of 10 seconds or less.This condition was identified when a nearby instrumentation line was found frozen and brought into question the operability of the safety-related MFIVs.(The frozen instrument line had no adverse effect on plant operation.) | | NAME TELEPHONE NUMBER (rncrvde Area Code) |
| This event was caused by a combination of inadequate design and improper functioning of the HVAC system that serves the Steam Tunnel (area that MFIVs are located in).The steam tunnel HVAC supply fans (S64 Fan and S65 Fan)take a suction from the outside atmosphere and exhaust directly into the area of the MFIVs.They are designed with an automatic low ambient temperature shutoff at 30 degrees, but plant process computer data indicates that the fans continued to o'perate with outside temperatures well below the 30 degree setpoint.Even if the fans had shutoff as designed at 30 degrees, MFIV actuator temperatures may have dropped to just slightly below the minimum MFIV actuator operating temperature of 60 degrees.This LER revision is being provided to more accurately describe the initial corrective actions taken to address the steam tunnel low tern erature conditions and to inco orate additional actions taken to date.9807i 6028i'2)8070')F PDR ADQCK 05000400 NRC FORM 366A (4.65I LICENSEE EVENT REPORT (LER)'EXT CONTINUATION US.NUCLEAR REGULATORY COMIAISSION FACILITY NAME (Il Shearon Harris Nuclear Plant~Unit¹1 DOCKET 50 400 97-002 01 LER NUMBER (6I YEAR EQUENTIAL NUMBER NUMBER PAGE (3I 2 OF 3 TEXT iii more speoe ri rerioded.ose eddi(ioool oopres ol iVRC Form 36Q/(Ill EVEsNT DESCRIPTION; On February 7, 1997, with the plant operating in Mode 1 at 100%power, investigation determined that technical specification 4.6.3 had been violated.Specifically, cold weather conditions resulted in the Main Feedwater Isolation Valves (MFIVs)being potentially inoperable during a period from January 17, 1997 through January 20, 1997.The MFIVs serve as containment isolation valves and are required to stroke closed in 10 seconds or less to provide feedwater isolation in the event of a main steam line break or spurious opening of a feedwater regulating valve.This isolation function will prevent excessive Reactor Coolant System cooldown and/or Containment over pressurization. | | Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| Based on purchase specification documents and discussions with the MFIV vendor, a minimum operating temperature of 60 degrees exists to ensure that the MFIVs will stroke in the required 10 seconds.The MFIV actuators are hydraulic to open and shut with nitrogen pressure, but even the shut sequence utilizes hydraulic oil operation. | | REPORTABLE REPORTABLE CAUSE SYSTEM CONIPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPROS TO NPROS VF FAN J127 SUPPLEMENTAL REPORT EXPECTED {14) EXPECTED MONTH OAY YEAR YES SUBMISSION (If yos, complete EXPECTED SUBMISSION DATE). X NO DATE {16) |
| Therefore, with actuator temperature below 60 degrees the hydraulic oil may be too viscous to provide a valve stroke time of 10 seconds or less.This condition was identified when a nearby instrumentation line for the"C" main feedwater bypass line fiow transmitter was found frozen and brought into question the operability of the safety-related MFIVs.(The frozen flow transmitter instrument line had no,adverse affect on plant operation.) | | ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) |
| Investigation into this condition revealed deficiencies in the design and operation of the HVAC system that serves the steam tunnel area where the MFIVs are located.The steam tunnel HVAC supply fans (S64 Fan and S65 Fan)take a suction from the outside atmosphere and exhaust directly into the area of the MFIVs.They are designed with an automatic low ambient temperature shutoff at 30 degrees, but archived plant process computer data indicates that the S65 fan continued to operate with outside temperatures well below the 30 degree setpoint.The"C" MFIV actuator is positioned directly in the exhaust path of one of the S65 Fan duct openings and is approximately 10 feet above the area where the flow transmitter line was found frozen.A review of data taken since the event shows that temperatures in the area of the MFIV actuators run approximately 15 to 20 degrees greater than the location of the frozen instrument line.Based on this, using a simplistic engineering approach, the'temperature of all three MFIV actuators would have been below the 60 degree minimum operating limit and were therefore potentially inoperable (incapable of performing containment isolation function in 10 seconds).CAUSE: This event was caused by a combination of inadequate design and improper functioning of the steam tunnel HVAC system.The steam tunnel HVAC supply fans (S64 Fan and S65 Fan)take a suction from the outside atmosphere and exhaust directly into the area of the MFIVs.They are designed with an automatic low ambient temperature shutoff at 30 degrees, but plant process computer data indicates that the fans continued to operate with outside temperatures below the 30 degree set'point. | | On February 7, 1997, with the plant operating in Mode 1 at 100% power, investigation determined that cold weather conditions resulted in the Main Feedwater Isolation Valves (MFIVs) being potentially inoperable during a period from January 17, 1997 through January 20, 1997. The MFIVs serve as containment isolation valves and are required to stroke closed in 10 seconds or less. to provide feedwater isolation in the event of a main steam line break or spurious opening of a feedwater regulating valve. Based on purchase specification documents and discussions with the MFIV vendor, a minimum operating temperature of 60 degrees exists to ensure that the MFIVs will stroke in the required 10 seconds. The" MFIV actuators are hydraulic to open and shut with nitrogen pressure, but even the shut sequence utilizes hydraulic oil operation. Therefore, with actuator temperature below 60 degrees the hydraulic oil may be too viscous to provide a valve stroke time of 10 seconds or less. This condition was identified when a nearby instrumentation line was found frozen and brought into question the operability of the safety-related MFIVs. (The frozen instrument line had no adverse effect on plant operation.) |
| Additional research has shown that if the fans had shutoff as designed at an outside ambient temperature of 30 degrees, MFIVs actuator operating temperature may have dropped to just slightly below the 60 degree operating band minimum.SAFETY SIGNIFICANCE: | | This event was caused by a combination of inadequate design and improper functioning of the HVAC system that serves the Steam Tunnel (area that MFIVs are located in). The steam tunnel HVAC supply fans (S64 Fan and S65 Fan) take a suction from the outside atmosphere and exhaust directly into the area of the MFIVs. They are designed with an automatic low ambient temperature shutoff at 30 degrees, but plant process computer data indicates that the fans continued to o'perate with outside temperatures well below the 30 degree setpoint. Even if the fans had shutoff as designed at 30 degrees, MFIV actuator temperatures may have dropped to just slightly below the minimum MFIV actuator operating temperature of 60 degrees. |
| There were no adverse safety consequences associated with this event.This is based on engineering review and probabilistic safety analysis performed for Harris Plant LER¹96-006, (submitted April 24, 1996)which determined that the failure of a MFIV to perform its containment isolation function was non-safety significant. | | This LER revision is being provided to more accurately describe the initial corrective actions taken to address the steam tunnel low tern erature conditions and to inco orate additional actions taken to date. |
| The potential consequences of a MFIV failing to close are over-filling the affected Steam Generator and subsequent over-cooling of the Reactor Coolant System.This would be mitigated by plant design features (tripping of the main'feedwater pumps or automatic closure of the feedwater regulating valves), or by operator intervention to control the main feedwater system.This is being reported per 10CFR50.73.a.2.i.B as a violation of Technical Specifications. | | 9807i 6028i '2)8070')F PDR ADQCK 05000400 |
| PREVIOUS SIMILAR EVENTS: There have been no other previous reports submitted related to MFIVs being rendered inoperable due to cold weather conditions. | | |
| LER 96-006 (referenced above)was submitted due to a MFIV valve stem failure that occurred during surveillance testing.NRCF RM A I4 I NRC FORM 3BBA (4-95l~LICENSEE EVEitiT REPORT (LERj TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (I)Shearon Harris Nuclear Plant~Unit 41 TEXT pl more spore is receded, vse eddirr'ooel oopas ol AiRC Form 3'(l (ITI OOCKET 5O4OO LER NUMBER (BI YEAR SEQUENTIAL REVlSION NUMBER NUMBER 97 002 01 PAGE (3I 3 OF 3 CORRECTIVE ACTIONS COMPLETED: | | NRC FORM 366A US. NUCLEAR REGULATORY COMIAISSION (4.65I LICENSEE EVENT REPORT (LER) |
| 1.Additional investigation and troubleshooting was performed on the steam tunnel HVAC system design and operational configuration. | | 'EXT CONTINUATION FACILITY NAME (Il DOCKET LER NUMBER (6I PAGE (3I YEAR EQUENTIAL NUMBER NUMBER Shearon Harris Nuclear Plant ~ |
| This resulted in modifications to the system that were implemented by Engineering Service Requests (ESRs)97-00157 and 97-00785.ESR 97-00157 was a permanent modification that adjusted the high temperature setpoint of the steam tunnel thermocouple that feeds the S-64 and S-65 Supply Fans thermocouple from 90 to 70 degrees.ESR 97-00785 was a temporary modification that: (1)moved the physical location of the thermocouples to elliminate inaccuracies, and (2)adjusted the low temperature setpoint for the Steam Tunnel Fans from 30 to 43 degrees.Although the physical changes have been implemented as described in both ESRs, the temporary modification (ESR 97-00785)will be made permanent and closed out upon completion of a FQ Program evaluation. | | Unit ¹1 50 400 2 OF 3 97 - 002 01 TEXT iiimore speoe ri rerioded. ose eddi(ioool oopres ol iVRC Form 36Q/ (Ill EVEsNT DESCRIPTION; On February 7, 1997, with the plant operating in Mode 1 at 100% power, investigation determined that technical specification 4.6.3 had been violated. Specifically, cold weather conditions resulted in the Main Feedwater Isolation Valves (MFIVs) being potentially inoperable during a period from January 17, 1997 through January 20, 1997. The MFIVs serve as containment isolation valves and are required to stroke closed in 10 seconds or less to provide feedwater isolation in the event of a main steam line break or spurious opening of a feedwater regulating valve. This isolation function will prevent excessive Reactor Coolant System cooldown and/or Containment over pressurization. |
| A Justification for Continued Operation (JCO 98-02)was g'enerated for the steam tunnel temperature control issue while the aforementioned EQ evaluation is in progress.The basis, for this JCO was provided by ESR 98-00016.The JCO will also be canceled upon completion of the EQ Program evaluation which will allow close out of the temporary modification ESR 97-00785.3.Revisions were made to the Daily Surveillance Requirement Operations Surveillance Test procedures (OST-1021&OST-1022)to ensure that when outside ambient temperature is less than 65 degrees, steam tunnel temperatures will be locally monitored once per 6 hours by Operations personnel. | | Based on purchase specification documents and discussions with the MFIV vendor, a minimum operating temperature of 60 degrees exists to ensure that the MFIVs will stroke in the required 10 seconds. The MFIV actuators are hydraulic to open and shut with nitrogen pressure, but even the shut sequence utilizes hydraulic oil operation. Therefore, with actuator temperature below 60 degrees the hydraulic oil may be too viscous to provide a valve stroke time of 10 seconds or less. |
| 4.Revisions were made to the Reactor Auxiliary Building HVAC System Operating Procedure (OP-172)and System Description (SD-172)to clarify system operation.
| | This condition was identified when a nearby instrumentation line for the "C" main feedwater bypass line fiow transmitter was found frozen and brought into question the operability of the safety-related MFIVs. (The frozen flow transmitter instrument line had no,adverse affect on plant operation.) Investigation into this condition revealed deficiencies in the design and operation of the HVAC system that serves the steam tunnel area where the MFIVs are located. The steam tunnel HVAC supply fans (S64 Fan and S65 Fan) take a suction from the outside atmosphere and exhaust directly into the area of the MFIVs. They are designed with an automatic low ambient temperature shutoff at 30 degrees, but archived plant process computer data indicates that the S65 fan continued to operate with outside temperatures well below the 30 degree setpoint. |
| 5.As an interim measure, an Operations Night Order was issued to provide additional emphasis on the proper operation of the Steam Tunnel HVAC System.N h'I A (4 5l}}
| | The "C" MFIV actuator is positioned directly in the exhaust path of one of the S65 Fan duct openings and is approximately 10 feet above the area where the flow transmitter line was found frozen. A review of data taken since the event shows that temperatures in the area of the MFIV actuators run approximately 15 to 20 degrees greater than the location of the frozen instrument line. Based on this, using a simplistic engineering approach, the'temperature of all three MFIV actuators would have been below the 60 degree minimum operating limit and were therefore potentially inoperable (incapable of performing containment isolation function in 10 seconds). |
| | CAUSE: |
| | This event was caused by a combination of inadequate design and improper functioning of the steam tunnel HVAC system. |
| | The steam tunnel HVAC supply fans (S64 Fan and S65 Fan) take a suction from the outside atmosphere and exhaust directly into the area of the MFIVs. They are designed with an automatic low ambient temperature shutoff at 30 degrees, but plant process computer data indicates that the fans continued to operate with outside temperatures below the 30 degree set'point. Additional research has shown that if the fans had shutoff as designed at an outside ambient temperature of 30 degrees, MFIVs actuator operating temperature may have dropped to just slightly below the 60 degree operating band minimum. |
| | SAFETY SIGNIFICANCE: |
| | There were no adverse safety consequences associated with this event. This is based on engineering review and probabilistic safety analysis performed for Harris Plant LER ¹96-006, (submitted April 24, 1996) which determined that the failure of a MFIV to perform its containment isolation function was non-safety significant. The potential consequences of a MFIV failing to close are over-filling the affected Steam Generator and subsequent over-cooling of the Reactor Coolant System. This would be mitigated by plant design features (tripping of the main'feedwater pumps or automatic closure of the feedwater regulating valves), or by operator intervention to control the main feedwater system. |
| | This is being reported per 10CFR50.73.a.2.i.B as a violation of Technical Specifications. |
| | PREVIOUS SIMILAR EVENTS: |
| | There have been no other previous reports submitted related to MFIVs being rendered inoperable due to cold weather conditions. LER 96-006 (referenced above) was submitted due to a MFIV valve stem failure that occurred during surveillance testing. |
| | NRCF RM A I4 I |
| | |
| | NRC FORM 3BBA U.S. NUCLEAR REGULATORY COMMISSION (4-95l ~ |
| | LICENSEE EVEitiT REPORT (LERj TEXT CONTINUATION FACILITY NAME (I) OOCKET LER NUMBER (BI PAGE (3I SEQUENTIAL REVlSION YEAR NUMBER NUMBER Shearon Harris Nuclear Plant ~ Unit 41 5O4OO 3 OF 3 97 002 01 TEXT pl more spore is receded, vse eddirr'ooel oopas ol AiRC Form 3'(l (ITI CORRECTIVE ACTIONS COMPLETED: |
| | : 1. Additional investigation and troubleshooting was performed on the steam tunnel HVAC system design and operational configuration. This resulted in modifications to the system that were implemented by Engineering Service Requests (ESRs) 97-00157 and 97-00785. ESR 97-00157 was a permanent modification that adjusted the high temperature setpoint of the steam tunnel thermocouple that feeds the S-64 and S-65 Supply Fans thermocouple from 90 to 70 degrees. ESR 97-00785 was a temporary modification that: (1) moved the physical location of the thermocouples to elliminate inaccuracies, and (2) adjusted the low temperature setpoint for the Steam Tunnel Fans from 30 to 43 degrees. Although the physical changes have been implemented as described in both ESRs, the temporary modification (ESR 97-00785) will be made permanent and closed out upon completion of a FQ Program evaluation. |
| | A Justification for Continued Operation (JCO 98-02) was g'enerated for the steam tunnel temperature control issue while the aforementioned EQ evaluation is in progress. The basis, for this JCO was provided by ESR 98-00016. The JCO will also be canceled upon completion of the EQ Program evaluation which will allow close out of the temporary modification ESR 97-00785. |
| | : 3. Revisions were made to the Daily Surveillance Requirement Operations Surveillance Test procedures (OST-1021 & OST-1022) to ensure that when outside ambient temperature is less than 65 degrees, steam tunnel temperatures will be locally monitored once per 6 hours by Operations personnel. |
| | : 4. Revisions were made to the Reactor Auxiliary Building HVAC System Operating Procedure (OP-172) and System Description (SD-172) to clarify system operation. |
| | : 5. As an interim measure, an Operations Night Order was issued to provide additional emphasis on the proper operation of the Steam Tunnel HVAC System. |
| | N h'I A (4 5l}} |
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC SysML18016A484 |
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Harris |
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07/07/1998 |
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Verrilli M CAROLINA POWER & LIGHT CO. |
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ML18016A483 |
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LER-97-002, LER-97-2, NUDOCS 9807160281 |
Download: ML18016A484 (3) |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18022B0551998-05-20020 May 1998 LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr ML18016A4061998-04-30030 April 1998 LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive ML18016A3841998-04-13013 April 1998 LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr ML18016A3441998-03-12012 March 1998 LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV ML18016A3291998-02-27027 February 1998 LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr ML18016A3211998-02-20020 February 1998 LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr ML18016A3131998-02-0909 February 1998 LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01 ML18016A2641997-12-18018 December 1997 LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr ML18016A2501997-11-24024 November 1997 LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr ML18016A2201997-10-22022 October 1997 LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures ML18016A2081997-10-14014 October 1997 LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr ML18016A2111997-10-14014 October 1997 LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced ML18016A1931997-09-29029 September 1997 LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr ML18016A1891997-09-12012 September 1997 LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr ML18016A1881997-09-12012 September 1997 LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr ML18012A8641997-08-18018 August 1997 LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr ML18012A8581997-08-0808 August 1997 LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc ML18012A8551997-08-0808 August 1997 LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls ML18012A8471997-07-31031 July 1997 LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr ML18012A8371997-07-24024 July 1997 LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold ML18012A8291997-07-11011 July 1997 LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr ML18012A8301997-07-0808 July 1997 LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr ML18012A8241997-07-0202 July 1997 LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr ML18022B0181997-06-13013 June 1997 LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr ML18012A8081997-06-0909 June 1997 LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr ML18012A8021997-06-0606 June 1997 LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr ML18012A8011997-06-0404 June 1997 LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr ML18012A7951997-05-29029 May 1997 LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr ML18012A7891997-05-22022 May 1997 LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr ML18012A7871997-05-19019 May 1997 LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr ML18012A7761997-05-0707 May 1997 LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr ML18012A7751997-05-0505 May 1997 LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr ML18012A6291997-04-24024 April 1997 LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr ML18022B0151997-04-17017 April 1997 LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr ML18012A6041997-04-0303 April 1997 LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr ML18012A6031997-03-31031 March 1997 LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr 1999-09-10
[Table view] Category:RO)
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18022B0551998-05-20020 May 1998 LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr ML18016A4061998-04-30030 April 1998 LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive ML18016A3841998-04-13013 April 1998 LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr ML18016A3441998-03-12012 March 1998 LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV ML18016A3291998-02-27027 February 1998 LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr ML18016A3211998-02-20020 February 1998 LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr ML18016A3131998-02-0909 February 1998 LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01 ML18016A2641997-12-18018 December 1997 LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr ML18016A2501997-11-24024 November 1997 LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr ML18016A2201997-10-22022 October 1997 LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures ML18016A2081997-10-14014 October 1997 LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr ML18016A2111997-10-14014 October 1997 LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced ML18016A1931997-09-29029 September 1997 LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr ML18016A1891997-09-12012 September 1997 LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr ML18016A1881997-09-12012 September 1997 LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr ML18012A8641997-08-18018 August 1997 LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr ML18012A8581997-08-0808 August 1997 LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc ML18012A8551997-08-0808 August 1997 LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls ML18012A8471997-07-31031 July 1997 LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr ML18012A8371997-07-24024 July 1997 LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold ML18012A8291997-07-11011 July 1997 LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr ML18012A8301997-07-0808 July 1997 LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr ML18012A8241997-07-0202 July 1997 LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr ML18022B0181997-06-13013 June 1997 LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr ML18012A8081997-06-0909 June 1997 LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr ML18012A8021997-06-0606 June 1997 LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr ML18012A8011997-06-0404 June 1997 LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr ML18012A7951997-05-29029 May 1997 LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr ML18012A7891997-05-22022 May 1997 LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr ML18012A7871997-05-19019 May 1997 LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr ML18012A7761997-05-0707 May 1997 LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr ML18012A7751997-05-0505 May 1997 LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr ML18012A6291997-04-24024 April 1997 LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr ML18022B0151997-04-17017 April 1997 LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr ML18012A6041997-04-0303 April 1997 LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr ML18012A6031997-03-31031 March 1997 LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr 1999-09-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A9151999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18017A8621999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18017A8361999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr ML18016B0151999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr ML18017A8981999-05-12012 May 1999 Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines. ML18016A9581999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8941999-04-0505 April 1999 Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760 ML18016A9101999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr ML18016A8661999-03-31031 March 1999 Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept. ML18017A8931999-02-28028 February 1999 Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant. ML18016A8551999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8531999-02-18018 February 1999 Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'. ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18022B0631999-02-0404 February 1999 Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings ML20202J1161999-02-0101 February 1999 SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program ML18016A8041999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7801998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr ML18016A7671998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr ML18016A9731998-11-28028 November 1998 Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr ML18016A8351998-11-28028 November 1998 ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1. ML18016A7411998-11-25025 November 1998 Rev 1 to Shnpp Cycle 9 Colr. ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A7071998-11-0303 November 1998 Rev 0 to Harris Unit 1 Cycle 9 Colr. ML18016A7201998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves ML18016A6201998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr ML18016A5971998-09-21021 September 1998 Rev 1 to Harris Unit 1 Cycle 8 Colr. ML18016A5881998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr ML18016A5071998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr ML18016A9431998-07-0707 July 1998 Rev 1 to QAP Manual. ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A9371998-06-30030 June 1998 Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp. ML18016A4861998-06-30030 June 1998 Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18016A4521998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr ML18016A7711998-05-26026 May 1998 Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'. 1999-09-30
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NRC FORM 366 U.S. NU EAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150.0104 H.B5) EXPIRES 04/30/96 ESTIMATED BUROEH PER RESPOt(SE TO COMPLY yt(TH THIS MAt(DATORY INFORMATION COllECTIOII REOUEST: 50O HRS. REPORTED lESSONS LEARNED ARE LXCENSEE EVENT REPORT (LER) (NCORPORATEO lt(TO THE UCENSLNG PROCESS ANO FEO BACK TO U(OUSTRY.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION ANO RECORDS MANAGEMENT BRANCH IT4) F33). US. NUCLEAR REGULATORY COMMISSION, (See reverse for required number of WASHINGTON. DC 20555()00), AND TO THE PAPERWORK REDUCTION PROJECT gl50.
digits/characters for each block) 010(). OFFICE OF h(ANAGEh'IENT ANO BUDGET, WASH(t(GTON, DC 20503.
FACILITY NAME (1I DOCKET NUMBER (2) PAGE (3)
Harris Nuclear Plant Unit-1 50-400 1OF3 TITLE (4)
Inoperable Main Feedwater Isolation Valves caused by cold weather conditions.
EVENT DATE (5) LER NUMBER (6) REPORT DATE {7) OTHER FACILITIES INVOLVED (6)
FACIL(TY NAME DOCKET NUMBER SEQUENTIAL REVISION MONTH OAY YEAR MONTH DAY NUMBER NUMBER FACIUTY NAME DOCKET NUMBER 2 7 97 97 002 01 07 07 98 05000 OPERATING THIS REPORT IS SUBMITTED PUR SUANT TO THE REQUIREMENTS OF 10 CFR E: (Chock ona or more) (11)
MODE (9) 20.2201(b) 20.2203(a) (2) (v) 50.73(a) (2) (i) 50.73(a)(2)(viii) 20.2203(a) (1) 20.2203(a) (3) (i) 50.73(a)(2)(ii) 50.73(a)(2)(x)
POWER 100o LEVEL (10) 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) OTHER 20.2203(a) (2) (iii) 50.36(c)(1) 50.73(a) {2){v) Specify ln Abstract be(ow or in NRC Form 366A 20.2203(a) (2) (iv) 50.36(c) (2) 50.73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (rncrvde Area Code)
Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
REPORTABLE REPORTABLE CAUSE SYSTEM CONIPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPROS TO NPROS VF FAN J127 SUPPLEMENTAL REPORT EXPECTED {14) EXPECTED MONTH OAY YEAR YES SUBMISSION (If yos, complete EXPECTED SUBMISSION DATE). X NO DATE {16)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On February 7, 1997, with the plant operating in Mode 1 at 100% power, investigation determined that cold weather conditions resulted in the Main Feedwater Isolation Valves (MFIVs) being potentially inoperable during a period from January 17, 1997 through January 20, 1997. The MFIVs serve as containment isolation valves and are required to stroke closed in 10 seconds or less. to provide feedwater isolation in the event of a main steam line break or spurious opening of a feedwater regulating valve. Based on purchase specification documents and discussions with the MFIV vendor, a minimum operating temperature of 60 degrees exists to ensure that the MFIVs will stroke in the required 10 seconds. The" MFIV actuators are hydraulic to open and shut with nitrogen pressure, but even the shut sequence utilizes hydraulic oil operation. Therefore, with actuator temperature below 60 degrees the hydraulic oil may be too viscous to provide a valve stroke time of 10 seconds or less. This condition was identified when a nearby instrumentation line was found frozen and brought into question the operability of the safety-related MFIVs. (The frozen instrument line had no adverse effect on plant operation.)
This event was caused by a combination of inadequate design and improper functioning of the HVAC system that serves the Steam Tunnel (area that MFIVs are located in). The steam tunnel HVAC supply fans (S64 Fan and S65 Fan) take a suction from the outside atmosphere and exhaust directly into the area of the MFIVs. They are designed with an automatic low ambient temperature shutoff at 30 degrees, but plant process computer data indicates that the fans continued to o'perate with outside temperatures well below the 30 degree setpoint. Even if the fans had shutoff as designed at 30 degrees, MFIV actuator temperatures may have dropped to just slightly below the minimum MFIV actuator operating temperature of 60 degrees.
This LER revision is being provided to more accurately describe the initial corrective actions taken to address the steam tunnel low tern erature conditions and to inco orate additional actions taken to date.
9807i 6028i '2)8070')F PDR ADQCK 05000400
NRC FORM 366A US. NUCLEAR REGULATORY COMIAISSION (4.65I LICENSEE EVENT REPORT (LER)
'EXT CONTINUATION FACILITY NAME (Il DOCKET LER NUMBER (6I PAGE (3I YEAR EQUENTIAL NUMBER NUMBER Shearon Harris Nuclear Plant ~
Unit ¹1 50 400 2 OF 3 97 - 002 01 TEXT iiimore speoe ri rerioded. ose eddi(ioool oopres ol iVRC Form 36Q/ (Ill EVEsNT DESCRIPTION; On February 7, 1997, with the plant operating in Mode 1 at 100% power, investigation determined that technical specification 4.6.3 had been violated. Specifically, cold weather conditions resulted in the Main Feedwater Isolation Valves (MFIVs) being potentially inoperable during a period from January 17, 1997 through January 20, 1997. The MFIVs serve as containment isolation valves and are required to stroke closed in 10 seconds or less to provide feedwater isolation in the event of a main steam line break or spurious opening of a feedwater regulating valve. This isolation function will prevent excessive Reactor Coolant System cooldown and/or Containment over pressurization.
Based on purchase specification documents and discussions with the MFIV vendor, a minimum operating temperature of 60 degrees exists to ensure that the MFIVs will stroke in the required 10 seconds. The MFIV actuators are hydraulic to open and shut with nitrogen pressure, but even the shut sequence utilizes hydraulic oil operation. Therefore, with actuator temperature below 60 degrees the hydraulic oil may be too viscous to provide a valve stroke time of 10 seconds or less.
This condition was identified when a nearby instrumentation line for the "C" main feedwater bypass line fiow transmitter was found frozen and brought into question the operability of the safety-related MFIVs. (The frozen flow transmitter instrument line had no,adverse affect on plant operation.) Investigation into this condition revealed deficiencies in the design and operation of the HVAC system that serves the steam tunnel area where the MFIVs are located. The steam tunnel HVAC supply fans (S64 Fan and S65 Fan) take a suction from the outside atmosphere and exhaust directly into the area of the MFIVs. They are designed with an automatic low ambient temperature shutoff at 30 degrees, but archived plant process computer data indicates that the S65 fan continued to operate with outside temperatures well below the 30 degree setpoint.
The "C" MFIV actuator is positioned directly in the exhaust path of one of the S65 Fan duct openings and is approximately 10 feet above the area where the flow transmitter line was found frozen. A review of data taken since the event shows that temperatures in the area of the MFIV actuators run approximately 15 to 20 degrees greater than the location of the frozen instrument line. Based on this, using a simplistic engineering approach, the'temperature of all three MFIV actuators would have been below the 60 degree minimum operating limit and were therefore potentially inoperable (incapable of performing containment isolation function in 10 seconds).
CAUSE:
This event was caused by a combination of inadequate design and improper functioning of the steam tunnel HVAC system.
The steam tunnel HVAC supply fans (S64 Fan and S65 Fan) take a suction from the outside atmosphere and exhaust directly into the area of the MFIVs. They are designed with an automatic low ambient temperature shutoff at 30 degrees, but plant process computer data indicates that the fans continued to operate with outside temperatures below the 30 degree set'point. Additional research has shown that if the fans had shutoff as designed at an outside ambient temperature of 30 degrees, MFIVs actuator operating temperature may have dropped to just slightly below the 60 degree operating band minimum.
SAFETY SIGNIFICANCE:
There were no adverse safety consequences associated with this event. This is based on engineering review and probabilistic safety analysis performed for Harris Plant LER ¹96-006, (submitted April 24, 1996) which determined that the failure of a MFIV to perform its containment isolation function was non-safety significant. The potential consequences of a MFIV failing to close are over-filling the affected Steam Generator and subsequent over-cooling of the Reactor Coolant System. This would be mitigated by plant design features (tripping of the main'feedwater pumps or automatic closure of the feedwater regulating valves), or by operator intervention to control the main feedwater system.
This is being reported per 10CFR50.73.a.2.i.B as a violation of Technical Specifications.
PREVIOUS SIMILAR EVENTS:
There have been no other previous reports submitted related to MFIVs being rendered inoperable due to cold weather conditions. LER 96-006 (referenced above) was submitted due to a MFIV valve stem failure that occurred during surveillance testing.
NRCF RM A I4 I
NRC FORM 3BBA U.S. NUCLEAR REGULATORY COMMISSION (4-95l ~
LICENSEE EVEitiT REPORT (LERj TEXT CONTINUATION FACILITY NAME (I) OOCKET LER NUMBER (BI PAGE (3I SEQUENTIAL REVlSION YEAR NUMBER NUMBER Shearon Harris Nuclear Plant ~ Unit 41 5O4OO 3 OF 3 97 002 01 TEXT pl more spore is receded, vse eddirr'ooel oopas ol AiRC Form 3'(l (ITI CORRECTIVE ACTIONS COMPLETED:
- 1. Additional investigation and troubleshooting was performed on the steam tunnel HVAC system design and operational configuration. This resulted in modifications to the system that were implemented by Engineering Service Requests (ESRs) 97-00157 and 97-00785. ESR 97-00157 was a permanent modification that adjusted the high temperature setpoint of the steam tunnel thermocouple that feeds the S-64 and S-65 Supply Fans thermocouple from 90 to 70 degrees. ESR 97-00785 was a temporary modification that: (1) moved the physical location of the thermocouples to elliminate inaccuracies, and (2) adjusted the low temperature setpoint for the Steam Tunnel Fans from 30 to 43 degrees. Although the physical changes have been implemented as described in both ESRs, the temporary modification (ESR 97-00785) will be made permanent and closed out upon completion of a FQ Program evaluation.
A Justification for Continued Operation (JCO 98-02) was g'enerated for the steam tunnel temperature control issue while the aforementioned EQ evaluation is in progress. The basis, for this JCO was provided by ESR 98-00016. The JCO will also be canceled upon completion of the EQ Program evaluation which will allow close out of the temporary modification ESR 97-00785.
- 3. Revisions were made to the Daily Surveillance Requirement Operations Surveillance Test procedures (OST-1021 & OST-1022) to ensure that when outside ambient temperature is less than 65 degrees, steam tunnel temperatures will be locally monitored once per 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> by Operations personnel.
- 4. Revisions were made to the Reactor Auxiliary Building HVAC System Operating Procedure (OP-172) and System Description (SD-172) to clarify system operation.
- 5. As an interim measure, an Operations Night Order was issued to provide additional emphasis on the proper operation of the Steam Tunnel HVAC System.
N h'I A (4 5l