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| {{#Wiki_filter:June 02, 1989 U.S. Nuclear Regulatory Commission. | | {{#Wiki_filter:VIRGINIA ELECTRIC ANO POWER COMPANY Surry , _ , Station P. 0. Boa 315 Surry, Virginia 23883 June 02, 1989 U.S. Nuclear Regulatory Commission. Serial No.: 89-017 Document Control Desk Docket No.: 50-280 016 Phillips Building 50-281 Washington, D.C. 20555 License No.: DPR-32 DPR-37 Gentlemen: |
| Document Control Desk 016 Phillips Building Washington, D.C. 20555 Gentlemen:
| | Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Eve~t Report for Units 1 & 2. |
| VIRGINIA ELECTRIC ANO POWER COMPANY Surry ,_, Station P. 0. Boa 315 Surry, Virginia 23883 Serial No.: 89-017 Docket No.: 50-280 50-281 License No.: DPR-32 DPR-37 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Eve~t Report for Units 1 & 2. REPORT NUMBER | | REPORT NUMBER |
| * 89-015-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control. Very truly yours, Station.Manager. | | * 89-015-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control. |
| Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 8906090270 890602 PDR ADOCK O~OOO?RO ::: -*---i=*oc: - | | Very truly yours, Station.Manager. |
| NRC Form 366 (9-83) FACILITY NAME (1) LICENSEE EVENT REPORT (LER) U.S. NUCLEAR REGULATORY COMMISSION APPROVED OM a NO. 3160-0104 EXPIRES: 8/31/88 Surry Power Station, Units 1 and 2 I DOCKET NUMBER (21 I PAGE (31 o I 5 Io Io Io 12 1 810 1 loF O I 3 TITLE (4) Setpoints Required for Auto Start of Fire Pumps Do Not Correspond to T,S, Requirements EVENT DATE (5) LER NUMBER (61 REPORT DATE (7) OTHER FACILITIES INVOLVED (8) MONTH DAY YEAR YEAR :::::::::: | | Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 8906090270 890602 PDR ADOCK O~OOO?RO |
| SEQUENTIAL(::::::::: | | ::: -*- - -i=*oc: - |
| REVISION MONTH :::::;:::: | | |
| NUMBER ~:::::::::: | | NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION (9-83) |
| NUMBER DAY YEAR FACILITY NAMES DOCKET NUMBER(S) o I s o Is 8 9 8 I 9 -o 11 1s -o 10 o I 6 o 12 8 I 9 OPERATING MODE (9) THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock ono or moro of tho follo~ing/ | | APPROVED OM a NO. 3160-0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (21 I PAGE (31 TITLE (4) |
| (11) 20.402(b) | | Surry Power Station, Units 1 and 2 Io I 5 Io Io Io 12 1 810 1 loF OI 3 Setpoints Required for Auto Start of Fire Pumps Do Not Correspond to T,S, Requirements EVENT DATE (5) LER NUMBER (61 REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| POWER I 20.406(a)(1
| | MONTH DAY YEAR YEAR :::::::::: SEQUENTIAL(::::::::: REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S) |
| )(i) LEVEL -1101 I 1 20.40s1.11111;;1 20.406(el(1 lliii) 20.406(al(1)llv) 20,406(*)(1 | | :::::;:::: NUMBER ~:::::::::: NUMBER o I s oIs 8 9 8 I9 - o11 1s - o10 oI6 o12 8 I9 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock ono or moro of tho follo~ing/ (11) |
| )(vi 20.405(c) | | MODE (9) |
| -60.36(c)(1) | | I 20.402(b) |
| -50.36(c)(2)
| | - 20.405(c) 60.73(a)(2)(iv) 73.71(b) |
| -X 50.73(a) (2)(i) >---60,73(a)(2)(ii)
| | POWER 20.406(a)(1 )(i) 60.36(c)(1) 60.73(a)(2)(v) 73.71 (c) |
| --50.73(e)(2lliiil LICENSEE CONTACT FOR THIS LER (12) 60.73(a)(2)(iv)
| | LEVEL - >-- |
| >--60.73(a)(2)(v)
| | 1101 I 1 20.40s1.11111;;1 50.36(c)(2) 60.73(o)(2)(vii) OTHER (Spocify in Abstract |
| >--60.73(o)(2)(vii)
| | >-- below and in Texr, NRC Form 20.406(el(1 lliii) X 50.73(a) (2)(i) 60.73(1)(2)(viiil(A) 366A) 20.406(al(1)llv) 20,406(*)(1 )(vi - 60,73(a)(2)(ii) 50.73(e)(2lliiil 60,73(a)(2)(viii)(B) 60.73lall2ll*I LICENSEE CONTACT FOR THIS LER (12) |
| >--60.73(1)(2)(viiil(A) 60,73(a)(2)(viii)(B) 60.73lall2ll*I 73.71(b) 73.71 (c) OTHER (Spocify in Abstract below and in Texr, NRC Form 366A) NAME TELEPHONE NUMBER AREA CODE M.' R. Kansler, Station Manager 8 IO I 4 3 15 I 7 I -13 I i l 8 14 COMPLETE ONE LINE FOR EACf; COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 CAUSE SYSTEM COMPONENT TURER REPORTABLE
| | NAME TELEPHONE NUMBER AREA CODE M.' R. Kansler, Station Manager 8 IO I 4 3 15 I 7 I - 13 I i l 8 14 COMPLETE ONE LINE FOR EACf; COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC- REPORTABLE :.:.:::::*: ., .. ,., ::::--\:: :,::: |
| :.:.:::::*: | | CAUSE SYSTEM COMPONENT MANUFAC-TURER TO NPRDS ): .... CAUSE SYSTEM COMPONENT TURER I I I I I I I .*.:. ..... I I I I I I I I I I I I I I *.*.*..*.-;.: .,. .*.*.:.: ,....,. |
| ., .. ,., ::::--\:: | | I I I I I *1 I *:-::*:*:*:*:*:-:.;.;.:: *:*:*:*:*:*:*:*:* |
| :,::: TO NPRDS ): .... CAUSE SYSTEM COMPONENT TURER .*:-:* .... ::::: *.*.* :*.*.* .:.:*.: . . *.: :.:.:.::*:* | | SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED I YES /If yes, comploto EXPECTED SUBMISSION DATE/ |
| :*:*: -:* .*:* .*.: I I I I I I I .*.:. . .... I I I I I I I ... ,.* .. *.-;.: *:*::*.-*.*:*:-::*.* | | ABSTRACT (Limit to 1400 spacss, i.e., approximately fifteen single-space typewritten lines) (16) bl NO SUBMISSION DATE (15) |
| .. , .... , .. *.* .. *.-*.*.*.* .. *.* I I I I I I I . ,.*.*:*:* | | I I I On May 5, 1989 during a review of a change request for a fire protection system surveillance test, it was noted that the setpoints required for the automatic starts of the fire protection pumps did not appear to correspond to the requirements in Surry's Technical Specifications (T.S.). |
| *.: . *.*. I I I I I *1 I *.*.* .. *.-;.: . ,. .*.*.:.: , .... , . SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED SUBMISSION I YES /If yes, comploto EXPECTED SUBMISSION DATE/ bl NO DATE (15) ABSTRACT (Limit to 1400 spacss, i.e., approximately fifteen single-space typewritten lines) (16) NRC Form 366 19*831 On May 5, 1989 during a review of a change request for a fire protection system surveillance test, it was noted that the setpoints required for the automatic starts of the fire protection pumps did not appear to correspond to the requirements in Surry's Technical Specifications (T.S.). The motor driven and diesel driven fire pumps' autostart setpoints are 90 + 4 psig and 80 + 4 psig, respectively.
| | The motor driven and diesel driven fire pumps' autostart setpoints are 90 + 4 psig and 80 + 4 psig, respectively. |
| However, T.S. 4.Y8.B.l.f(3) requires the pumps to maintain system pressure equal to or greater than 90 psig. Therefore, the diesel pump would technically be considered inoperable and the motor driven pump would be inoperable if the setpoint drifted below 90 psig. Operability of the fire protection pumps is required by T.S. 3.21.A.2.a.
| | However, T.S. 4.Y8.B.l.f(3) requires the pumps to maintain system pressure equal to or greater than 90 psig. |
| An engineering evaluation will be performed to change the pumps' start setpoints to 80 psig and a T.S. change will be submitted.
| | Therefore, the diesel pump would technically be considered inoperable and the motor driven pump would be inoperable if the setpoint drifted below 90 psig. Operability of the fire protection pumps is required by T.S. 3.21.A.2.a. An engineering evaluation will be performed to change the pumps' start setpoints to 80 psig and a T.S. change will be submitted. In the interim, the fire pump automatic start setpoints have been changed to comply with Technical Specifications. The applicable Periodic Test will be revised accordingly. |
| In the interim, the fire pump automatic start setpoints have been changed to comply with Technical Specifications.
| | NRC Form 366 19*831 |
| The applicable Periodic Test will be revised accordingly.
| | |
| :.*.:*:::*:*:*:*:*:-:*:*:*:*:*:*:*:*:*:*:*:*:*:
| | NRC 1-orm . .A U.S. NUCLEAR REGULATORY COMMISSION 111-831 LICENSEE E - T REPORT (LERI TEXT CONTINUA-N APPROVED 0MB NO 3150-01Gc EXPIRES: 8/31/8.< |
| ,:.;.:::::::::::::::::::,:,::, ... ;*:*:*:*:*:*:*:*
| | FACILITY NAME 111 DOCKET NUMBER 12: |
| *:-::*:*:*:*:*:-:.;.;.::
| | I LER NUMBER 16* |
| *:*:*:*:*:*:*:*:*
| | *,*-:***tSEOUENTIAL *.*.*IRE VIS ID"" |
| MONTH DAY YEAR I I I NRC 1-orm .. A 111-831 FACILITY NAME 111 LICENSEE E-T REPORT (LERI TEXT CONTINUA-N U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO 3150-01Gc EXPIRES: 8/31/8.< DOCKET NUMBER 12: I YEAR LER NUMBER 16* *,*-:***tSEOUENTIAL NUM!!!IE R *.*.*IRE VIS ID"" ***lNUM!ER PAGE 13 Surry Power Station, Units 1 and 2 I 8 I 9 -0 I (I 5 -1 0 I O O i 2 I° F O 13 TEXT Ill mon, .-ce o -* u* --NRC form 3li6.A '*11171 NRC FORM 366.t. 19-83, 1.0 Description of the Event 2.0 On May 5, 1989 during a review of a change request for a fire protection system (EIIS-KP) surveillance test, it was noted that the setpoints required for the automatic starts of the fire protection pumps (EIIS-P) did not appear to correspond to the requirements in Surry's Technical Specifications.
| | PAGE 13 YEAR NUM!!!IE R ***lNUM!ER I |
| The surveillance requirements in T.S. 4.18.B.l.f(3) states that "the fire suppression water system shall be demonstrated operable at least once per 18 months by verifying that each high pressure pump starts (sequentially) to maintain the fire suppression water system pressure equal to or greater than 90 psig". Contrary to this requirement, the automatic setpoints for the motor driven and diesel driven fire pumps are 90 + 4 psig and 80 + 4 psig, respectively. | | TEXT Ill Surry Power Station, Units 1 and 2 mon, .-ce o - |
| Failure of the fire pumps to meet their performance requirement as specified in T.S. Section 4 surveillance requirements would technically render the pumps inoperable per the T.S. definition of operability.
| | * u* - - NRC form 3li6.A '*11171 8I 9 - 0 I (I 5 -1 0 I O O i 2 I° F O 13 1.0 Description of the Event On May 5, 1989 during a review of a change request for a fire protection system (EIIS-KP) surveillance test, it was noted that the setpoints required for the automatic starts of the fire protection pumps (EIIS-P) did not appear to correspond to the requirements in Surry's Technical Specifications. The surveillance requirements in T.S. 4.18.B.l.f(3) states that "the fire suppression water system shall be demonstrated operable at least once per 18 months by verifying that each high pressure pump starts (sequentially) to maintain the fire suppression water system pressure equal to or greater than 90 psig". Contrary to this requirement, the automatic setpoints for the motor driven and diesel driven fire pumps are 90 + 4 psig and 80 + 4 psig, respectively. Failure of the fire pumps to meet their performance requirement as specified in T.S. Section 4 surveillance requirements would technically render the pumps inoperable per the T.S. definition of operability. Operability of the fire protection pumps is required by T.S. 3.21.A.2.a. |
| Operability of the fire protection pumps is required by T.S. 3.21.A.2.a.
| | 2.0 Safety Consequences and Implications The fire water system is maintained at a static pressure of 100 to 110 psig by a maintenance pump and a hydropneumatic. tank. A motor driven pump and a diesel driven pump, each with a capacity of 2500 gpm at a dynamic head of 231 feet, are provided to supply fire water for the plant's fire suppression system upon demand. Either of these pumps can provide the required flow to maintain system pressure at greater than 90 psig to ensure operability of the system. An automatic start of the motor driven fire pump would occur when fire water demand decreased system pressure to less than 90 psig. Should the motor driven pump fail to start, the diesel driven pump would automatically start at a pressure of 80 psig. The additional time required for the automatic start of the diesel pump, due to the lower start setpoint, would be insignificant and would have no effect on the operability of the fire suppression system. |
| Safety Consequences and Implications The fire water system is maintained at a static pressure of 100 to 110 psig by a maintenance pump and a hydropneumatic.
| | Therefore, the health and safety of the public were not affected. |
| tank. A motor driven pump and a diesel driven pump, each with a capacity of 2500 gpm at a dynamic head of 231 feet, are provided to supply fire water for the plant's fire suppression system upon demand. Either of these pumps can provide the required flow to maintain system pressure at greater than 90 psig to ensure operability of the system. An automatic start of the motor driven fire pump would occur when fire water demand decreased system pressure to less than 90 psig. Should the motor driven pump fail to start, the diesel driven pump would automatically start at a pressure of 80 psig. The additional time required for the automatic start of the diesel pump, due to the lower start setpoint, would be insignificant and would have no effect on the operability of the fire suppression system. Therefore, the health and safety of the public were not affected.
| | NRC FORM 366.t. .:.,; * . j ~ ti C' - * * - :,r- ,, \*( |
| .:.,; * . j ti C' -* * -:,r-,, \*(
| | 19-83, |
| NRC rorm .. A 19-831 FACILITY NAME 11 I LICENSEE EV.T REPORT (LERI TEXT CONTINUAT-DOCKET NUMBER 121 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO 31 50--0lC'C EXPIRES: 8/31/8!< LEA NUMBER 16, I PAGE IJ YEAR . *.-:***ISEOUENTIAL
| | |
| * *'IREVISIO
| | NRC rorm . .A U.S. NUCLEAR REGULATORY COMMISSION 19-831 LICENSEE EV.T REPORT (LERI TEXT CONTINUAT- APPROVED 0MB NO 31 50--0lC'C EXPIRES: 8/31/8!< |
| .... Surry Power Station, Units 1 and 2 NUM(IIECI
| | FACILITY NAME 11 I DOCKET NUMBER 121 LEA NUMBER 16, I PAGE IJ |
| ** NUM!IER Jo,l o 1s101o10J2 J8IO 819 -o 11 Is -TEXT fll_mor._,.
| | . *.-:***ISEOUENTIAL * *'IREVISIO .... |
| __ ., .. -NRCk>nn.l15&111'*11171 NRC FORM 386.A 19-BJ, 3.0 Cause In 1984, the Technical Specification surveillance requirements were reviewed to verify that procedures existed to ensure compliance with the Technical Specifications.
| | Jo,l YEAR NUM(IIECI ** NUM!IER Surry Power Station, Units 1 and 2 TEXT fll_mor._,. _ _ .,.. -NRCk>nn.l15&111'*11171 o 1s101o10J2 J8IO 819 -o 11 Is - oI o 0 i 13 3.0 Cause In 1984, the Technical Specification surveillance requirements were reviewed to verify that procedures existed to ensure compliance with the Technical Specifications. At the time of the review, the T.S. |
| At the time of the review, the T.S. was interpreted to mean that the pumps would be required to start sequentially but not necessarily at a pressure greater than 90 psig since the system pressure would be maintained at 90 psig after the pumps started. Since Periodic Tests existed to assure this performance, the requirements were considered to be met. In addition, the Updated Final Safety Analysis Report, Section 9.10.2.2., states that the motor driven fire pump would automatically start when system pressure drops below 90 psig, and the diesel driven pump would start if the system pressure continued to drop. It is assumed this information was used as a basis for establishing the original start setpoints.
| | was interpreted to mean that the pumps would be required to start sequentially but not necessarily at a pressure greater than 90 psig since the system pressure would be maintained at 90 psig after the pumps started. Since Periodic Tests existed to assure this performance, the requirements were considered to be met. In addition, the Updated Final Safety Analysis Report, Section 9.10.2.2., states that the motor driven fire pump would automatically start when system pressure drops below 90 psig, and the diesel driven pump would start if the system pressure continued to drop. It is assumed this information was used as a basis for establishing the original start setpoints. |
| 4.0 Immediate Corrective Action(s) | | 4.0 Immediate Corrective Action(s) |
| An Engineering Work Request was initiated to evaluate changing the fire pump automatic start setpoints. | | An Engineering Work Request was initiated to evaluate changing the fire pump automatic start setpoints. |
| 5.0 Additional Corrective Action(s) | | 5.0 Additional Corrective Action(s) |
| An engineering evaluation has been performed to justify changing the required pump start setpoints to greater than or equal to 80 psig and a T.S. change request will be submitted. | | An engineering evaluation has been performed to justify changing the required pump start setpoints to greater than or equal to 80 psig and a T.S. change request will be submitted. In the interim; the fire pump automatic start setpoints have been changed to 95 |
| In the interim; the fire pump automatic start setpoints have been changed to 95 + 4, -0 psig and 90 + 4, -0 psig for the motbr driven and diesel driven pumps, respectively. | | + 4, -0 psig and 90 + 4, -0 psig for the motbr driven and diesel driven pumps, respectively. The applicable Periodic Tests will be revised accordingly. |
| The applicable Periodic Tests will be revised accordingly. | | 6.0 Action(s) Taken to Prevent Recurrence None required. |
| 6.0 Action(s) | | 7.0 Similar Events N/A 8.0 Manufacturer/Model Number(s) |
| Taken to Prevent Recurrence None required. | | N/A |
| 7.0 Similar Events N/A 8.0 Manufacturer/Model Number(s) | | * * , .", , - |
| N/A o I o 0 i 13 * * , .", , -* I ., I'\ t' * -* ' * :"I I"~* \ I (}} | | * I ., I'\ t' * - * ' * :"I I"~* \I( |
| | NRC FORM 386.A 19-BJ,}} |
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LER 97-005-00:on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled
ML18153A1291997-04-18018 April 1997
LER 97-006-00:on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B.W/970418 Ltr
ML18153A1281997-04-15015 April 1997
LER 97-004-00:on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions performed.W/970415 Ltr
ML18153A1241997-04-0808 April 1997
LER 97-002-01:on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust linkage.W/970408 Ltr
ML18153A1191997-03-19019 March 1997
LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr
ML18153A1201997-03-19019 March 1997
LER 97-003-00:on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified open.W/970319 Ltr
ML18153A1131997-02-20020 February 1997
LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr
ML18153A1101997-02-13013 February 1997
LER 97-002-00:on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116.W/970214 Ltr
ML18153A0951997-01-0202 January 1997
LER 97-002-00:on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown
ML18153A0931996-12-12012 December 1996
LER 96-008-00:on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers replaced.W/961212 Ltr
ML18153A0691996-09-19019 September 1996
LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr
ML18153A0481996-08-26026 August 1996
LER 96-005-00:on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other tubing.W/960826 Ltr
ML18153A0521996-08-20020 August 1996
LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr
ML18153A0321996-07-30030 July 1996
LER 96-006-01:on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to batteries.W/960730 Ltr
ML18153A0281996-07-17017 July 1996
LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr
ML18153A0141996-07-0202 July 1996
LER 96-004-00:on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status trees.W/960702 Ltr
1999-08-27
[Table view]
Category:RO)
MONTHYEARML18152B4411999-08-27027 August 1999
LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18152B4421999-08-27027 August 1999
LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr
ML18152B3771999-08-13013 August 1999
LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18152B4181999-05-18018 May 1999
LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr
ML18152B4111999-04-28028 April 1999
LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr
ML18153A2741999-03-29029 March 1999
LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
ML18153A2681999-03-19019 March 1999
LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML18152B7261999-01-21021 January 1999
LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B5811998-12-16016 December 1998
LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5781998-12-16016 December 1998
LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998
LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened
ML18152B7041998-12-0101 December 1998
LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr
ML18152B6161998-11-0606 November 1998
LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable
ML18152B6081998-10-23023 October 1998
LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely
ML18152B7811998-07-31031 July 1998
LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
ML18153A2581998-06-0303 June 1998
LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
ML18152B8241998-05-22022 May 1998
LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
ML18153A2201998-02-0606 February 1998
LER 98-001-00:on 980108,deficient Test Due to Faulty Test Equipment Resulted in TS Violation.Caused by Faulty Vibration Analyzer Cable or Loose Connection.Station Deviation Rept Was submitted.W/980206 Ltr
ML18153A2071998-01-13013 January 1998
LER 97-012-01:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors
ML18153A2101998-01-13013 January 1998
LER 97-009-01:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status
ML18153A1911997-11-26026 November 1997
LER 97-011-00:on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised
ML18153A1971997-11-26026 November 1997
LER 97-012-00:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Breaker in Security Distribution Panel in Central Alarm Station (CAS) Panel.Breakers in Affected CAS Panel Reset
ML18153A1921997-11-25025 November 1997
LER 97-010-00:on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared operable.W/971125 Ltr
ML18153A1831997-11-12012 November 1997
LER 97-009-00:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Cause Indeterminate.Divers Inspected,Cleaned & Returned Probes to Operable Status & Initiated Interdepartmental Team to Investigate Cause
ML18153A1791997-11-0707 November 1997
LER 97-008-00:on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset
ML18153A1721997-10-30030 October 1997
LER 97-007-00:on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage
ML18153A1421997-06-10010 June 1997
LER 97-001-01:on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation circuitry.W/970610 Ltr
ML18153A1391997-05-28028 May 1997
LER 97-005-00:on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled
ML18153A1291997-04-18018 April 1997
LER 97-006-00:on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B.W/970418 Ltr
ML18153A1281997-04-15015 April 1997
LER 97-004-00:on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions performed.W/970415 Ltr
ML18153A1241997-04-0808 April 1997
LER 97-002-01:on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust linkage.W/970408 Ltr
ML18153A1191997-03-19019 March 1997
LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr
ML18153A1201997-03-19019 March 1997
LER 97-003-00:on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified open.W/970319 Ltr
ML18153A1131997-02-20020 February 1997
LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr
ML18153A1101997-02-13013 February 1997
LER 97-002-00:on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116.W/970214 Ltr
ML18153A0951997-01-0202 January 1997
LER 97-002-00:on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown
ML18153A0931996-12-12012 December 1996
LER 96-008-00:on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers replaced.W/961212 Ltr
ML18153A0691996-09-19019 September 1996
LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr
ML18153A0481996-08-26026 August 1996
LER 96-005-00:on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other tubing.W/960826 Ltr
ML18153A0521996-08-20020 August 1996
LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr
ML18153A0321996-07-30030 July 1996
LER 96-006-01:on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to batteries.W/960730 Ltr
ML18153A0281996-07-17017 July 1996
LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr
ML18153A0141996-07-0202 July 1996
LER 96-004-00:on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status trees.W/960702 Ltr
1999-08-27
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999
Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619.
ML18152B3531999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr
ML18152B6651999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr
ML18152B4421999-08-27027 August 1999
LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr
ML18152B4411999-08-27027 August 1999
LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18151A3981999-08-13013 August 1999
SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage.
ML18152B3771999-08-13013 August 1999
LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18152B3791999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr
ML18152B3911999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr
ML18152B4341999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr
ML20195E2401999-05-31031 May 1999
Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag
ML18152B4181999-05-18018 May 1999
LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr
ML18152B4161999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr
ML18152B4111999-04-28028 April 1999
LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr
ML18152B6511999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2
ML18153A2741999-03-29029 March 1999
LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
ML18153A2681999-03-19019 March 1999
LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML18152B7331999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr
ML18152B5421999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr
ML18151A3031999-01-29029 January 1999
ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements.
ML18152B7261999-01-21021 January 1999
LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr
ML18152B5781998-12-16016 December 1998
LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5811998-12-16016 December 1998
LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998
LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened
ML18152B7041998-12-0101 December 1998
LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr
ML18152B7081998-11-30030 November 1998
Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un.
ML18152B5721998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr
ML18152B6161998-11-0606 November 1998
LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable
ML18152B6241998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr
ML18152B6081998-10-23023 October 1998
LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely
ML18152B6881998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr
ML18153A3271998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2
ML18152B7811998-07-31031 July 1998
LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
ML18153A3161998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr
ML18152B7621998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr
ML18153A2581998-06-0303 June 1998
LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML18153A3141998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610
ML18152B8241998-05-22022 May 1998
LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B8161998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML20217P9941998-04-0707 April 1998
Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024
ML18153A2951998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
1999-09-30
[Table view] |
Text
VIRGINIA ELECTRIC ANO POWER COMPANY Surry , _ , Station P. 0. Boa 315 Surry, Virginia 23883 June 02, 1989 U.S. Nuclear Regulatory Commission. Serial No.: 89-017 Document Control Desk Docket No.: 50-280 016 Phillips Building 50-281 Washington, D.C. 20555 License No.: DPR-32 DPR-37 Gentlemen:
Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Eve~t Report for Units 1 & 2.
REPORT NUMBER
- 89-015-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control.
Very truly yours, Station.Manager.
Enclosure cc: Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 8906090270 890602 PDR ADOCK O~OOO?RO
- -*- - -i=*oc: -
NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION (9-83)
APPROVED OM a NO. 3160-0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (21 I PAGE (31 TITLE (4)
Surry Power Station, Units 1 and 2 Io I 5 Io Io Io 12 1 810 1 loF OI 3 Setpoints Required for Auto Start of Fire Pumps Do Not Correspond to T,S, Requirements EVENT DATE (5) LER NUMBER (61 REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR :::::::::: SEQUENTIAL(::::::::: REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S)
- NUMBER ~
- ::::::::: NUMBER o I s oIs 8 9 8 I9 - o11 1s - o10 oI6 o12 8 I9 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock ono or moro of tho follo~ing/ (11)
MODE (9)
I 20.402(b)
- 20.405(c) 60.73(a)(2)(iv) 73.71(b)
POWER 20.406(a)(1 )(i) 60.36(c)(1) 60.73(a)(2)(v) 73.71 (c)
LEVEL - >--
1101 I 1 20.40s1.11111;;1 50.36(c)(2) 60.73(o)(2)(vii) OTHER (Spocify in Abstract
>-- below and in Texr, NRC Form 20.406(el(1 lliii) X 50.73(a) (2)(i) 60.73(1)(2)(viiil(A) 366A) 20.406(al(1)llv) 20,406(*)(1 )(vi - 60,73(a)(2)(ii) 50.73(e)(2lliiil 60,73(a)(2)(viii)(B) 60.73lall2ll*I LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER AREA CODE M.' R. Kansler, Station Manager 8 IO I 4 3 15 I 7 I - 13 I i l 8 14 COMPLETE ONE LINE FOR EACf; COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC- REPORTABLE :.:.:::::*: ., .. ,., ::::--\:: :,:::
CAUSE SYSTEM COMPONENT MANUFAC-TURER TO NPRDS ): .... CAUSE SYSTEM COMPONENT TURER I I I I I I I .*.:. ..... I I I I I I I I I I I I I I *.*.*..*.-;.: .,. .*.*.:.: ,....,.
I I I I I *1 I *:-::*:*:*:*:*:-:.;.;.:: *:*:*:*:*:*:*:*:*
SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED I YES /If yes, comploto EXPECTED SUBMISSION DATE/
ABSTRACT (Limit to 1400 spacss, i.e., approximately fifteen single-space typewritten lines) (16) bl NO SUBMISSION DATE (15)
I I I On May 5, 1989 during a review of a change request for a fire protection system surveillance test, it was noted that the setpoints required for the automatic starts of the fire protection pumps did not appear to correspond to the requirements in Surry's Technical Specifications (T.S.).
The motor driven and diesel driven fire pumps' autostart setpoints are 90 + 4 psig and 80 + 4 psig, respectively.
However, T.S. 4.Y8.B.l.f(3) requires the pumps to maintain system pressure equal to or greater than 90 psig.
Therefore, the diesel pump would technically be considered inoperable and the motor driven pump would be inoperable if the setpoint drifted below 90 psig. Operability of the fire protection pumps is required by T.S. 3.21.A.2.a. An engineering evaluation will be performed to change the pumps' start setpoints to 80 psig and a T.S. change will be submitted. In the interim, the fire pump automatic start setpoints have been changed to comply with Technical Specifications. The applicable Periodic Test will be revised accordingly.
NRC Form 366 19*831
NRC 1-orm . .A U.S. NUCLEAR REGULATORY COMMISSION 111-831 LICENSEE E - T REPORT (LERI TEXT CONTINUA-N APPROVED 0MB NO 3150-01Gc EXPIRES: 8/31/8.<
FACILITY NAME 111 DOCKET NUMBER 12:
I LER NUMBER 16*
- ,*-:***tSEOUENTIAL *.*.*IRE VIS ID""
PAGE 13 YEAR NUM!!!IE R ***lNUM!ER I
TEXT Ill Surry Power Station, Units 1 and 2 mon, .-ce o -
- u* - - NRC form 3li6.A '*11171 8I 9 - 0 I (I 5 -1 0 I O O i 2 I° F O 13 1.0 Description of the Event On May 5, 1989 during a review of a change request for a fire protection system (EIIS-KP) surveillance test, it was noted that the setpoints required for the automatic starts of the fire protection pumps (EIIS-P) did not appear to correspond to the requirements in Surry's Technical Specifications. The surveillance requirements in T.S. 4.18.B.l.f(3) states that "the fire suppression water system shall be demonstrated operable at least once per 18 months by verifying that each high pressure pump starts (sequentially) to maintain the fire suppression water system pressure equal to or greater than 90 psig". Contrary to this requirement, the automatic setpoints for the motor driven and diesel driven fire pumps are 90 + 4 psig and 80 + 4 psig, respectively. Failure of the fire pumps to meet their performance requirement as specified in T.S. Section 4 surveillance requirements would technically render the pumps inoperable per the T.S. definition of operability. Operability of the fire protection pumps is required by T.S. 3.21.A.2.a.
2.0 Safety Consequences and Implications The fire water system is maintained at a static pressure of 100 to 110 psig by a maintenance pump and a hydropneumatic. tank. A motor driven pump and a diesel driven pump, each with a capacity of 2500 gpm at a dynamic head of 231 feet, are provided to supply fire water for the plant's fire suppression system upon demand. Either of these pumps can provide the required flow to maintain system pressure at greater than 90 psig to ensure operability of the system. An automatic start of the motor driven fire pump would occur when fire water demand decreased system pressure to less than 90 psig. Should the motor driven pump fail to start, the diesel driven pump would automatically start at a pressure of 80 psig. The additional time required for the automatic start of the diesel pump, due to the lower start setpoint, would be insignificant and would have no effect on the operability of the fire suppression system.
Therefore, the health and safety of the public were not affected.
NRC FORM 366.t. .:.,; * . j ~ ti C' - * * - :,r- ,, \*(
19-83,
NRC rorm . .A U.S. NUCLEAR REGULATORY COMMISSION 19-831 LICENSEE EV.T REPORT (LERI TEXT CONTINUAT- APPROVED 0MB NO 31 50--0lC'C EXPIRES: 8/31/8!<
FACILITY NAME 11 I DOCKET NUMBER 121 LEA NUMBER 16, I PAGE IJ
. *.-:***ISEOUENTIAL * *'IREVISIO ....
Jo,l YEAR NUM(IIECI ** NUM!IER Surry Power Station, Units 1 and 2 TEXT fll_mor._,. _ _ .,.. -NRCk>nn.l15&111'*11171 o 1s101o10J2 J8IO 819 -o 11 Is - oI o 0 i 13 3.0 Cause In 1984, the Technical Specification surveillance requirements were reviewed to verify that procedures existed to ensure compliance with the Technical Specifications. At the time of the review, the T.S.
was interpreted to mean that the pumps would be required to start sequentially but not necessarily at a pressure greater than 90 psig since the system pressure would be maintained at 90 psig after the pumps started. Since Periodic Tests existed to assure this performance, the requirements were considered to be met. In addition, the Updated Final Safety Analysis Report, Section 9.10.2.2., states that the motor driven fire pump would automatically start when system pressure drops below 90 psig, and the diesel driven pump would start if the system pressure continued to drop. It is assumed this information was used as a basis for establishing the original start setpoints.
4.0 Immediate Corrective Action(s)
An Engineering Work Request was initiated to evaluate changing the fire pump automatic start setpoints.
5.0 Additional Corrective Action(s)
An engineering evaluation has been performed to justify changing the required pump start setpoints to greater than or equal to 80 psig and a T.S. change request will be submitted. In the interim; the fire pump automatic start setpoints have been changed to 95
+ 4, -0 psig and 90 + 4, -0 psig for the motbr driven and diesel driven pumps, respectively. The applicable Periodic Tests will be revised accordingly.
6.0 Action(s) Taken to Prevent Recurrence None required.
7.0 Similar Events N/A 8.0 Manufacturer/Model Number(s)
N/A
- I ., I'\ t' * - * ' * :"I I"~* \I(
NRC FORM 386.A 19-BJ,
