ML18106A895

From kanterella
Jump to navigation Jump to search
LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr
ML18106A895
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/28/1998
From: Bakken A, Knieriem R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-012, LER-98-12, LR-N980449, NUDOCS 9810060338
Download: ML18106A895 (7)
v • d • e


Text

. *. *. _. *- e .. __ ..

, *=**

.. ,. - . .~---

..-~~*. *-.-. ~_:.. ~.

~~.~~-~-..*.

OPS~G

  • Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit SEP 2 8*1998 LR-N980449 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
  • This Supplemental Licensee Event Report entitled "22 Auxiliary Feedwater Pump lnoperability Caused By The F:ailure To Restore The Pump Runout Protection Pressure Transmitter To Service Following Calibration" is being submitted pursuant to the /

requirements of the Code of Federal Regulations ****10CFR50.73(a)(2)(1)(B) ****

Sincerely, A. C. Bakken Ill General Manager Salem Operations f

Attachment

/rbk C Distribution LER File 3.7 981 ~ wo928 r PDR ADOCK 0500031.

S_ PDR?i.,

The power is in your hands.

95-2168 REV. 6/94

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-1998) Estimated burden per response to comply with this mandatory information collection request 50 hrs. Reported lesson~ learned are incorporated into the licensing process and fed back to industry. Forward comments LICENSEE EVENT REPORT (LER) regarding burden estimate to the Records Management Branch IT-0 F33),

U.S. NuClear Regulatory Commission, Washington, DC 20555-0001, and to the Paperwork Reduction Project (3150-01_04), Office of Man.agement and (See reverse for required number of Budget, Washington, DC 20503. If an mfonnation collection does not digits/characters for each block) display a currenUy valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the infonnation collection.

FACl°LITY NAME (I) DOCKET NUMBER (2) PAGE(l)

Salem Unit 2 05000311 l OF 4 TITLEl4> 22 Auxiliary Feedwater Pump Inoperability Caused By The Failure To Restore The Pump Runout Protection Pressure Transmitter To Service Following Calibration SEQUENTIAL REVISION MONlH DAY YEAR YEAR NUMBER NUMBER MONlfl DAY YEAR 07 25 98 98 012 01 09 28 98 1 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)

OPERATING MODE(9) 20.220l(b) 20.2203(a)(2)(v) X S0.73(a)(2)(i) S0.73(a)(2)(viii) 20.2203(a)(I) 20.2203(a)(3)(i) S0.73(a)(2)(ii) SO. 73(a)(2)(x)

) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) S0.73(a)(2)(iii) 73.71

__...._..20_.2_2_03_(~aj-(2~)(~ii)..______..____2_0_22_0_3(_aj~(4~>--------+--t-s_o_.7_3(~a)_(2~)(~iv~>---------+--'OTHER

--+---.. . . . "'-'"'------+---+--------------+----.. . . ..-.....---------t 20.2203(a)(2)(iii) 20.2203(a)(2)(iv)

S0.36(c)(l) SO. 73(a)(2)(v)

SO. 73(a)(2)(vii)

Specify in Abstract below or in NRC Fonn 366A Robert B. Knieriem, Licensing Engineer (609) 339-1782 II COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT '13l II REPORTABLE

~:;~ REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX

~l

~llDDI 1'"MFNTA.I

~**-

lld.\ MONTH DAY YEAR EXPECTED SUBMISSION

'YES (If yes, complete EXPECTED SUBMISSION DATE). IX 'NO DATE(lS)

ABSTRACT (Limit to 1400 spaces, i.e., approximately IS single-spaced typewritten lines) (16)

This supplemental LER documents additional corrective action to be taken to address operation of Salem Unit 2 in a condition prohibited by Technical Specifications (TS). Contrary to TS 3.7.1.2, Auxiliary Feedwater System, Salem Unit 2 was operated with less than the required number of operable Auxiliary Feedwater (AFW) pumps.

This event is reportable under 10CFRS0.73(a) (2) (i) (B), any operation or condition prohibited by the plant's TS. TS 3.7.1.2 requires that for operation in Modes 1, 2, and 3, all three AFW pumps must be operable. During the period from July 7, 1998, i.mtil July 25, 1998, and without the knowledge of the operators, Salem Unit 2 was operated ia Mode 1 and Mode 2 with the 22 AFW pump inoperable. Following a calibration performed on July 7, 1998, technicians failed to restore the 22 AFW pump runout protection pressure device to service. With the runout protection pressure device isolated, the Steam Generator Flow Control valves would not open in response to an AFW pump discharge pressure signal. This condition would have prevented the 22 AFW pump from providing feedwater to the 21 and 22 Steam Generators when required.

The cause of this event was the failure of maintenance personnel to properly implement the procedure used to perform instrument calibrations. Specifically maintenance personnel failed to restore the 22 AFW pump runout protection pressure device to service following *calibration and failed to independently verify that the instrument had been returned to service.

" " " l"UKM ~vu (D-"'"a}

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998i LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET(l) LER NUMBER (6)

NUMBER'2l PAGE (3)

Salem Unit 2 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 05000311 98 - 012 - 01 2 OF 4 TEXT (If more space is required, use additionai copies of NRC Form 366A) (17)

Plant And System Identification Westinghouse - Pressur!zed Water Reactor Auxiliary Feedwater Pump {BA/P}

Auxiliary Feedwater Pump Runout Protection Pressure Transmitter {BA/PIC}

Auxiliary Feedwater Steam Generator Flow Control Valves {BA/FCV}

Steam Generator-Feed Pump {SJ/P}

Energy Industry Identification System (EIIS) system/component identifiers appear in {}

following the first reference to the system component.

Conditions Prior To Occurrence Mode 1, 100% power Description Of Occurrence On July 25, 1998, Salem Operations personnel were performing a plant shutdown in preparation for a planned maintenance outage. During the transition from the Steam Generator Feed pumps (SGFP) {SJ/P} to the Auxiliary Feedwater (AFW) pumps {BA/P},

operators noted that the Steam Generator Flow Control valves (21AF21 and 22AF21)

{BA/FCV} did not respond as expected following the start of the 22 AFW pump. The operators took manual control of the Steam Generator Flow Control valves and restored feedwater flow. At that time the 22 AFW pump was declared inoperable.

The 21AF21 and 22AF21 valves are used to regulate AFW flow to the 21 and 22 Steam Generators respectively. Additionally., these valves operate in response to a signal from the 22 AFW Pump Runout Pressure Transmitter (2PA3449) {BA/PIC}. This pressure transmitter senses pressure at the AFW pump discharge to provide runout protection for the AFW pumps. In response to 2PA3449, when AFW pump discharge pressure drops below 1200 psig, 21AF21 and 22AF21 begin to close. These valves are fully closed at an AFW pump discharge pressure of 1000 psig.

Upon further investigation, station personnel determined that the instrument valve for 2PA3449 was shut, isolating the instrument from the 22 AFW discparge. This prevented the 21AF21 and 22AF21 valves from operating in response to AFW ~µmp discharge pressure.

Upon discovery of this condition the instrument valve for 2PA3449 was opened and AFW pump runout protection.was restored. This action returned the 22 AFW pump to an operable condition and the Technical Specification action statement was exited.

Technical Specification 3.7.1.2, Auxiliary Feedwater System, requires that in Modes 1, 2, and 3, both motor-driven Auxiliary Feedwater pumps and the steam-driven Auxiliary Feedwater pump must be operable. With one AFW pump inoperable, Action a., of Technical Specification 3.7.1.2 requires that the inoperable pump must be restored to an operable status within seventy-two hours or the plant must be in at least Hot Standby within the next six hours and in Hot Shutdown within the following six hours.

NRC FORM 366A (6-1998)

\) NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION

  • ~ (6-1998)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION DOCKET(2)

FACILITY NAME. (I) NUMBER(2) LER NUMBER (6) PAGE (3)

YEAR I SEQUENTIAL NUMBER IREVISION NUMBER Salem Unit 2 05000311 98 012 01 3 OF 4 TEXT (If more space is required, use additional copies o/NRC Form 366A) (17)

Based upon a review of station operating and maintenance records, the 22 AFW Pump Runout Pressure Transmitter iastrument valve was last operated during the performance of an instrument calibration, performed on July.7, 1998. Following completion of that calibration, instrument technicians failed to properly restore the pressure transmitter to service. The instrument valve remained closed from July 7, 1998 until the discovery of this condition.on July 25, i998. During that period Salem Unit 2 operated in Mode 1 and Mode 2.

Apparent Cause Of Occurrence The apparent cause of this occurrence was the failure of maintenance personnel to properly implement the requirements of the Salem General Instrument Calibration Procedure For Field Devices (SC.IC-GP.ZZ-0003 (Q)), regarding equipment restoration.*

Following the completion of the instrument calibration on July 7, 1998, maintenance personnel did not restore the 22 AFW Pump Runout Protection Pressure Transmitter to service as required by SC.IC-GP.ZZ-0003 (Q). Specifically, maintenance personnel failed to follow the requirements of this procedure for restoring a pressure device to service following calibration and the requirement to independently verify that the instrument had been returned to service.

Prior Similar Occurrences A review of events during the past two years at Salem and Hope Creek Generating Stations identified one previous similar event. Hope Creek LER 354/97-009-00 reported an event in which the High Pressure Coolant Injection (HPCI) system was rendered inoperable after maintenance technicians failed to restore the HPCI Minimum Flow transmitter to service following calibration. The cause of that event was attributed to personnel performance, specifically verbatim procedure compliance and failure to properly conduct a hands-on second verification of the transmitter valves.

Safety Consequences The AFW pumps serve to supply feedwater to the secondary side of the Steam Generators at times when the Main Feedwater system is not available. The AFW:. system is relied upon to prevent Reactor Coolant System over-pressurization in the event pf accidents such as a loss of coolant accident, a loss of feedwater flow, a major feedwater line rupture, or a secondary system pipe rupture. In addition to accident and transient response, the AFW system is used to provide a means for plant cooldown.

Each Salem unit is equipped with one turbine-driven and two motor driven Auxiliary Feedwater pumps. Each motor-driven pump discharges to two of the four steam generators with a normally isolated cross-connect line joining the motor-driven pump discharge headers. The turbine-driven pump feeds all four steam generators. Feedwater flow is controlled from the Control Room by remotely operated flow control valves (AF21 valves for the motor-driven pumps and the AFll valves for the turbine driven pump) .

NRC FORM 366A (6-1998)

, I NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998)

LICENS~E EVENT REPORT (LER)

TEXT CONTINUATION DOCKET(l)

FACILITY NAME (I) NUMBER(l) LER NUMBER (6) PAGE (3)

YEAR I SEQUENTIAL NUMBER IREVISION NUMBER Salem Unit 2 05000311 98 - 012 - 01 4 OF 4 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

The AFW system is designed with adequate redundancy to provide reactor cooldown capability when required. Each pump has sufficient capacity to remove heat from the steam generators at a rate sufficient to prevent over-pressurization of the Reactor Coolant system and to maintain steam generator levels to prevent thermal cycling. With the 22 AFW pump inoperable, the othe.r two AFW pumps remained available, each capable of carrying out the design function of the system for the accidents analyzed.

In addition to the redundancy of the AFW pumps, the AFW pump runout protection device can be overridden in the control room. If an event had occurred in which a demand was placed upon the 22 AFW pump, the AF21 valves for the 22 AFW pump could have been overridden and flow restored to the 21 and 22 Steam Generators. This action is taken in accordance with appropriate procedural guidance.

Based upon the above, the inoperability of the 22 AFW pump Runout Pressure Transmitter did not place Salem Unit 2 in a condition that would impact the health and safety of the public.

Corrective Actions

1. The 22 AFW pump runout protection pressure transmitter was returned to service on July 25, 1998.
2. A valve lineup procedure was performed for instrument valves for the AFW system and the Residual Heat Removal system for Salem Units 1 and 2. No valve position deficiencies were identified.
3. All personnel involved have been held accountable in accordance with PSE&G's procedures and policies.
4. The details of this event were presented to Maintenance Department personnel as a written discussion of operating experience feedback. This discussion reinforced the importance of procedural compliance and independent verification in ensuring that components are restored the proper configuration following maintenance activities.
5. A review of Nuclear Business Unit programs and processes related. to the *control of safety system status will be performed to identify programmatic and organizational weaknesses that could compromise the ability of safety systems to carry out their design function. As a part of this review, the recommendations of INPO SOER 98-1 will be addressed. (PIR 980826176)

NRC FORM 366A (6-1998)

'"*I NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION DOCKET(l)

FACILITY NAME (I) NUMBER(l) LER NUMBER (6) PAGE(3)

YEAR I SEQUENTIAL NUMBER IREVISION NUMBER Salem Unit 2 05000311 98 012 01 3 OF 4 TEXT (If more space is required, use additional copies o/NRC Form 366A) (17)

Based upon a review of station operating and maintenance records, the 22 AFW Pump Runout Pressure Transmitter instrument valve was last operated during the performance of an instrument calibration performed on July 7, 1998. Following completion of that calibration, instrument technicians failed to properly restore the pressure*transmitter to service. The instrument valve remained closed from July 7, 1998 until the discovery of this condition on . July 25, 1998. During that period Salem Unit 2 operated in Mode 1 and Mode 2.

Apparent Cause Of Occurrence The apparent cause of this occurrence was the failure of maintenance personnel to properly implement the requirements of the Salem General Instrument Calibration Procedure For Field Devices (SC.IC-GP.ZZ-0003 (Q)), regarding equipment restoration.

Following the completion of the instrument calibration on July 7, 1998, maintenance personnel did not restore the 22 AFW Pump Runout Protection Pressure Transmitter to service as required by SC.IC-GP.ZZ-0003 (Q). Specifically, maintenance personnel failed to follow the requirements of this procedure for restoring a pressure device to service following calibration and the requirement to independently verify that the instrument had been returned to service.

Prior Similar Occurrences A review of events during the past two years at Salem and Hope Creek Generating Stations identified one previous similar event. Hope Creek LER 354/97-009-00 reported an event in which the High Pressure Coolant Injection (HPCI) system was rendered inoperable after maintenance technicians failed to restore the HPCI Minimum Flow transmitter to service following calibration. The cause of that event was attributed to personnel performance, specifically verbatim procedure compliance and failure to properly conduct a hands-on second verification of the transmitter valves.

Safety Conseguerices The AFW pumps serve to supply f eedwater to the secondary side of the Steam Generators at times when the Main Feedwater system is not available. The ~-system is relied upon to prevent Reactor Coolant System over-pressurization in the event of accidents such as a loss of coolant accident, a loss of feedwater flow, a major feedwater line rupture, or a secondary system pipe rupture. In addition to accident and transient response, the AFW system is used to provide a means for plant cooldown.

Each Salem unit is equipped with one turbine-driven and two motor driven Auxiliary Feedwater pumps. Each motor-driven pump discharges to two of the four steam generators

.with a normally isolated cross-connect line joining the motor-driven pump discharge headers. The turbine-driv.en pump feeds all four steam generators. Feedwater flow is controlled from the Control Room by remotely operated flow control valves (AF21 valves for the motor-driven pumps and the AFll valves for the turbine driven pump) .

NRC FORM 366A (6-1998)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION DOCKET (2)

FACILITY NAME (1) NUMBER(2) LER NUMBER (6) PAGE (3)

YEAR I SEQUENTIAL NUMBER IREVISION NUMBER Salem Unit 2 05000311 98 - 012 - 01 4 OF 4 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

The AFW system is designed with adequate redundancy to provide reactor cooldown capability when required. Each pump has sufficient capacity to remove heat from the steam generators at a rate sufficient to prevent over-pressurization of the Reactor Coolant system and to maintain steam generator levels to prevent thermal cycling. With the 22 AFW pump inoperable, the other two AFW pumps remained available, each capable of carrying out the design function of the system for the accidents analyzed.

In addition to the redundancy of the AFW pumps, the AFW pump runout protection device can be overridden in the control room. If an event had occurred in which a demand was placed upon the 22 AFW pump, the AF21 valves for the 22 AFW pump could have been overridden and flow restored to the 21 and 22 Steam Generators. This action is taken in accordance with appropriate procedural guidance.

Based upon the above, the inoperability of the 22 AFW pump Runout Pressure Transmitter did not place Salem Unit 2 in a condition that would impact the health and safety of the public.

Corrective Actions

1. The 22 AFW pump runout protection pressure transmitter was returned to service on July 25, 1998.
2. A valve lineup procedure was performed for instrument valves for the AFW system and the Residual Heat Removal system for Salem Units 1 and 2. No valve position deficiencies were identified.
3. All personnel involved have been held accountable in accordance with PSE&G's procedures and policies.
4. The details of this event were presented to Maintenance Department personnel as a written discussion of operating experience feedback. This discussion reinforced the importance of procedural compliance and independent verification in ensuring that components are restored the proper configuration following maintenance activities .
5. A review of Nuclear Business Unit programs and processes related to the control of safety system status will be performed to identify programmatic and organizational weaknesses that could compromise the ability of safety systems to carry out their design function. As a part of this review, the recommendations of INPO SOER 98-1 will be addressed. {PIR 980826176)

NRC FORM 366A (6-1998)

Retrieved from "https://kanterella.com/w/index.php?title=ML18106A895&oldid=2407309"