ML18096B168

LER 92-024-00:on 921123,SI Pump Declared Inoperable When Room Cooler Condensate Leakage Observed Leaking Onto Pump Motor.Caused by Design,Mfg,Const/Installation.Drip Bag Installed on Room Cooler drain.W/921221 Ltr

ML18096B168
Person / Time
Site:	Salem
Issue date:	12/21/1992
From:	POLLACK M J, VONDRA C A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-024, LER-92-24, NUDOCS 9212230248
Download: ML18096B168 (6)

Text

-e Public Service Electr_ic and Gas Company. P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-024-00 December 21 , 1-9 9 2 .This Licensee Event Report is being sµbmitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B). This report required to be issued within thirty (30) days of event discovery.

MJP:pc Distribution The Enerav F'eopie 9212230248 921221 PDR ADOCK -05000272 5 PDR Sincerely yours, c. AVondra General Manager -Salem Operations

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NRC FOJcM 366 16-89) U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 LICENSEE EVENT REPORT (LER) . FACILITY NAME (1) Salem Generating Station -Unit 1 TITLE 141 TS 3.0.3 Entry; Both SI Pumps :Inoperable EVENT DATE (5) LER NUMBER (6) REPORT DATE 17) MONTH DAY YEAR YEAR .it tt MONTH DAY YEAR 1 11 2 I 3 .9 2 9 I 2 -ol 214 o lo l I 2 2 I 1 9 12 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE' PAPERWORK REDUCTION PROJECT 13150-0104), OFFICE OF MANAGEMENT A.ND BUDGET, WASHINGTON, DC 20503 . I DOCKET NUMBER (2) I PAGE 131 o 15 I o Io I o 12 I 71 2 1 loF o 15 OTHER FACILITIES INVOLVED (Bl FACILITY NAMES DOCKET NUMBERISl OPERATING MODE IBl THIS REPORT IS SUBMITTED PURSUANT TO THE OF 10 CFR §: (Ch*ck one or mor* of th* following/

111) 20.4051cl 60.73l*ll2)(ivl 73.71lbl -i---1 20.402lbl

.........

--1----l 60.38lcll1l 60.73l*ll2lM 73.71lcl ---POWER I 20.4061*111)(1)

LEVEL l Q(Q -1101 1 20.4051011111111 50.381cll2l 60.73(e)(2)(vii)

OTHER (Spacify in Abstr*ct ---b*low *nd in Text, NRC Form x NAME 20.4051*111

)(iii) 20.406l*ll1lllvl 20.405l*ll1lM M. J. Pollack -LER Coordinator 50.731*ll2llil

--G0.731ell2lliil

--50.73l*ll2lliiil LICENSEE CONTACT FOR THIS LER 112) 60.73lell2llviiil1Al 60.731ell2llviiillBI 60.73lell2llxl AREA CODE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) CAUSE SYSTEM COMPONENT I I I I I I I I MANUFAC* TUR ER I I I I I I 111::1:!1j,i*j,:.j,.*:*1.:::.::.::,*1*::1!:!:J*::.:**

CAUSE SYSTEM I I COMPONENT MANUFAC* TUR ER I I I I I I I I I I I I 366A/ TELEPHONE NUMBER SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED SUBMISSION DATE 1151 n YES (If yes, comp/st* EXPECTED SUBMiSSION DATE} b:l NO I I ABSTRACT (Limit to 1400 spaces, i.e., approximately fifterm singfs.sjJsce typewritten lint1s} (16) On 11/23/92, the 11 Safety-Injection

{SI) Pump was declared inoperable when room cooler condensate leakage was observed leaking onto the pump's motor. Prior to this event, the 11 Service Water {SW) header had been removed from service making the 12 SI Pump inoperable due to inoperability of the lube oil cooler. Technical Specification 3.5.2 Actions do not apply with both SI Pumps declared inoperable; therefore, Tech. Spec. 3.0.3 was entered. A Unit shutdown commenced.

The cause of this event is "Design, Manufacturing, Construction/Installation".

The room cooler design includes a drip pan which collects condensate.

However, there is no drainage when the drip pan is full. The pan filled resulting in spillage onto the 11 SI Pump motor. Although the SI Pump motor is a "drip proof motor", the conservative approach was taken to declare the pump inoperable until it could be tested. A contributing factor to this event was that the room thermostat was found set at 60°F instead of ss°F. This thermostat is *interlocked with the room cooler (i.e., fan and SW valve position control).

Consequently, the room cooler was on constant run resulting in excessive condensate The thermostat was reset. The other Room Cooler thermostat controls were verified to be appropriately set. Testing of 11 SI Pump motor was successful.

The pump was declared operable and Tech. Spec. 3.0.3 was exited. Power had been reduced to 92%. Drain line installation, on those room coolers without condensate drip pan drain lines, is being assessed.

NRC Form 366 16*89) I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse

-Pressurized Water Reactor LER NUMBER 92-024-00 PAGE 2 of 5 Energy Industry Identification system (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:

Technical Specification

3.0.3 entry

both Safety Injection Pumps inoperable Event Date: 11/23/92 Report Date: 12/21/92 This report was initiated by Incident Report N6.92-780.

• CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 100% -Unit Load 1160 MWe . DESCRIPTION OF OCCURRENCE:

on November 23, 1992, at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, the 11 Safety Injection

• csI) Pump was declared inoperable when room cooler condensate leakage was observed leaking onto the pump's motor. Prior to this event, the 11 Service Water (SW) {BI} header had been removed from service to support Chiller SW piping repairs. Consequently, 12 SI Pump. lube oil cooler was inoperable due to lack of SW coolant flow. This made 12 SI Pump inoperable.

Technical Specification 3.5.2 Actions do not apply with both.SI Pumps declared inoperable; therefore, Technical Specification 3.0.3 was entered upon declaring 11 SI Pump inoperable.

The Nuclear Regulatory Commission was notified of the initiation of a controlled shutdown (per Technical Specification 3.0.3) on November 23, 1992, at 1011 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.846855e-4 months <br />, in accordance with Code of Federal Regulations lOCFR 50. 72 (b) (l)_(i) (A). Technical Specification

3.5.2 states

Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of the following.

injection systell\s:

... a. One.OPERABLE centrifugal charging pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and; 1. Discharging into each Reactor Coolant System LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 LER NUMBER 92-024-00 PAGE 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) (RCS) cold leg. b. One OPERABLE safety injection pump and flow path capable of taking suction from the refueling water storage tank and transferring suction to the heat removal pump discharge piping and; 1. Discharging into each RCS cold leg, and; upon initiation, 2. Discharging into its two associated RCS hot legs. c. One OPERABLE residual heat removal heat pump and etc." Technical Specification

3.0.3 states

"When a Limiting Condition for Operation is not met except as provided in the a?sociated ACTION requirements, within one hour action*shall be initiated to place the unit in a MODE in which the specification does not apply by placing.it, as applicable, in: 1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3. At least COLD SHUTDOWN within tbe subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> .. Where corrective measures are completed that permit operation under the ACTION 'requirements, the ACTION' may be*. taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition of Operation.

Exceptions to these requirements are stated in the individual specifications." APPARENT CAUSE OF OCCURRENCE:

The cause of this*event is "Design, Manufacturing, Construction/

Installation", per.NUREG.1022

{Licensee Event Report Program).

The room cooler design includes a.drip pan which collects condensate.

However, there is no drainage when the drip pan is full. The pan filled resulting in spillage onto the 11 SI Pump motor. Although the SI Pump motor is a "drip proof motor", the conservative approach_was taken to declare the pump inoperable until. *it could be tested .. A contributing factor to this event was that the room 'thermostat was found set at 60°F instead of ss°F. This thermostat is interlocked with the room cooler (i.e., fan and SW valve position control).

Consequently, the room .cooler was on constant run resulting in excessive condensate buildup. The as found thermostat setting did not affect operability of equipment in the.SI Pump Room. Also,

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--LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 APPARENT CAUSE OF OCCURRENCE: (cont'd) LER NUMBER 92-024-00 PAGE *4 of 5 system Engineering_

determined that no would affect component operability since its maximum setting is 100 F. ANALYSIS OF OCCURRENCE:

The Emergency Core Cooling system incorporates high head safety injection pumps (centrifugal charging pumps), intermediate head safety injection pumps (SI Pumps) and low. head safety injection pumps (Residual Heat Removal Pumps).* There are two of each type of pump where either pump .provides 100% of the flow requirements during ECCS operation.

In this event, 12 SI Pump was inoperable due to* 11 SW

• Header being out of service (as identified.in the Description of Occurrence Section).

11 SI Pump was cleared and tagged to support testing of its motor.

• Per Technical Specification 3.0.3, a Unit shutdown was commenced.*

On November 23, 1992, *.at 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br />, upon 11 SI Pump's return to service, the Specification was exited. Power hadbeen reduced to -92%. During the period of 11 SI Pump inoperability, safety injection was not required.

Also, the constraints of Technical 3.0.3 were met; therefore, .this event did not affect the health or safety of the public.

• Technical Specification 3.0.3 was required to be entered with both SI Pumps inoperable.

Therefore, this event is reportable to the Nuclear Regulatory Commission in accordance with the Code of Federal . Regulations lOCFR s9.73(a) (2) (i) (B). CORRECTIVE ACTION: Upon identification of the condensate overflow, the 11 SI Pump motor was wiped down. A drip bag was installed on the room cooler drain to collect condensate overflow.

Testing of 11 SI Pump motor to check *

• resistance (i.e. , 1 minute "megger" test) , was successful.

The motor was then started and acceptable current measurements were observed.

The pump was declared operable, at 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br />, on November 23, 1992 and Technical Specification

3. o .. 3 was exited and the Unit returned to full power operation.

The other.room coolers (e.g., Auxiliary Feedwater Pump area, *.. etc. ) were inspected.*

System Engineering is assessing whether drain line installation is needed on room coolers without drip pan drain lines. The incorrect as f ourtd setting of the SI Pump Room Cooler thermostat was corrected.

The other Salem Units 1 and 2 Room Cooler thermostat controls were verified to be appropriately set. I I !

.. *

• LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 CORRECTIVE ACTION: (cont'd) DOCKET NUMBER 5000272 LER NUMBER 92-024-00 PAGE 5 of 5 Room Cooler thermostats will be posted to indicate their intended function.

MJP:pc SORC Mtg.92-125 eneral Manager -Salem Operations I